IR 05000331/2019013: Difference between revisions

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{{Adams
{{Adams
| number = ML19252A192
| number = ML19345E136
| issue date = 09/06/2019
| issue date = 12/11/2019
| 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)
| title = Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000331/2019013
| author name = Hausman G
| author name = Daley R
| author affiliation = NRC/RGN-III/DRS/EB3
| author affiliation = NRC/RGN-III
| addressee name = Curtland D
| addressee name = Curtland D
| addressee affiliation = NextEra Energy Duane Arnold, LLC
| addressee affiliation = FPL 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 = Letter
| document type = Inspection Report, Letter
| page count = 6
| page count = 9
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:ber 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: DPR-49 Report Number: 05000331/2019013 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 Enclosure
 
=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) ===
{{IP sample|IP=IP 71111.17|count=28}}
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 Type              Designation    Description or Title                                  Revision or
Procedure                                                                                          Date
71111.17T Calculations      CAL-E98-004    Setpoint Calculation High Reactor Vessel Level, HPCI,  2
RCIC, Feedwater, and Turbine Trip in Remote Shutdown -
LS4540
CAL-MC-138    Diesel Oil Storage Tank Level Switch                  3
CAL-R17-002    Dose Rate Evaluation of Reactor Vessel Water Levels    0
During Refueling for EAL Thresholds
Corrective Action AR 01988025    NRC CGD [Commercial Grade Dedication] Inspection Issue 06/22/2015
Documents                        of Third Party Dedication
AR 02100600    NRC Questions on Use of [Recurring-Use Temporary      02/03/2016
Modification] RTM-04-OI151
AR 02102327    2016 50.59: Eval of Portable Heaters During Severe    08/08/2016
Weather
AR 02102503    AOP 903 - Severe Weather                              01/14/2016
AR 02102754    2016 50.59: Water Temperature Input to Mark I Analysis 02/22/2016
AR 02103084    2016 50.59: Inspection Identified Inadequate 50.59    01/26/2016
Screening
AR 02115464    RCIC Room Steam Leak Detection Not Consistent with CLB 10/02/2016
                                            [Current Licensing Basis]
AR 02138974    T.S. Bases Change Request: B3.3.6.1                    12/14/2016
AR 02138981    UFSAR Change Request: Chapter 7                        10/12/2016
AR 02139054    Evaluate Process Utilized to Move STP 3.5.1-03A/B to  09/23/2016
Online
AR 02175375    Power System Stabilizer 50.59                          01/18/2017
AR 02332637    2019 NRC 50.59/Mod Pre-Inspection Identified Items    10/24/2019
AR-LIC 2138981 DAEC UFSAR Chapter 7                                  06/20/2016
PCR 02073808  Annunciator Response Procedure ARP-1C22                40
Hydrogen/Oxygen Control Panel
PCR 02090816  Bases-ATWS (Anticipated Transient Without Scram)      19
PCR 02102503  AOP 903 Severe Weather, Revision 55                    01/14/2016
PCR 02225747  AOP 302.1 - Loss of 125 Vdc Power                      58
PCR 02259266  Biennial Review - ATWS - RPV Control,                  0
PCR 02266292  OI 878.1 - Source Range Neutron Monitoring System      21
Inspection Type              Designation    Description or Title                                      Revision or
Procedure                                                                                            Date
PCR 02268679  Annunciator Response Procedure ARP 1C22 -                42
Hydrogen/Oxygen Control Panel
PCR 02307806  AOP 302.1 - Loss of 125 Vdc Power                        60
Corrective Action AR 02337533    50.59 Screening for EC 290224                            12/05/2019
Documents
Resulting from
Inspection
Engineering      CA 02102327-01 Placement of Portable Heaters in the MG [Motor Generator] 07/01/2016
Changes                          Set Room
EC 0000156026  Replace Existing Reactor Feedwater Pumps (RFP) and        43
Motors with RFP and Motors of Larger Capacity
EC 0000283115  FIC2309 Replacement Siemens 353 Controller from Design    1
Level A to B
EC 0000283472  Fukushima Spent Fuel Pool Level Instrumentation          6
EC 0000283785  SBGT 1V-SGT-1A\B Flow Ind Controller Replacement          2
Siemens 353 Controller from Design Level A to B
FIC5828A/B
EC 0000283960  Raise All Level Setpoint for LS3701 to Allow Pump Starts  0
Due to Sticking LE3701 Float at Lowest Level
EC 0000285459  Connect Diesel Air Compressor to Plant Air System        0
EC 0000285499  CAL-E95-015 Calibration Frequency Revision                1
EC 0000285928  PLC 1701C Replacement                                    1
EC 0000286670  1K001-M Compressor Motor Overload Trip Jumper-ed Out      1
                                            (Bypassed)
EC 0000287838  Revise TE4403 Setpoint on TR4400 to Provide Annunciation  0
with Temperature Rise
EC 0000287965  Disable XR2 Low Oil Level Alarm to Prevent Masking Other  0
Alarms
EC 0000287997  RHR [Residual Heat Removal] Discharge Header Pressure    1
Switch Setpoint
EC 0000288156  TC6924A/B Control Building Chiller Temperature Controller 2
Siemens 353 Controller from Design Level A to B
EC 0000288815  Diesel Air Compressor Back-Up to Plant Air System        0
EC 0000289081  Revise CAL-M91-014 To Be in Compliance with              1
Inspection Type            Designation    Description or Title                                    Revision or
Procedure                                                                                          Date
ANSI 195-1976, Section 5.4
EC 0000291031  Reconfigure LS2219 Logic to Remove Automatic Opening of 2
SV2219
EC 0000291104  Replace LE-3768 with Longer Length Level Element        3
Engineering      ACE 01949946    2016 50.59: Eval of Portable Heaters During Severe      02/16/2016
Evaluations                      Weather
EC 0000281703  Chromalox Replacement Project                          0
EC 0000282458  RWS Cable Replacement                                  0
EC 0000287931  Implementation of Revised Calculations for LOCA Dose    0
Consequences
Miscellaneous    IP 71111.17T    Evaluations of Changes, Tests, and Experiments          01/01/2017
NEI 96-07      Guidelines for 10 CFR 50.59 Implementation              1
UCR #: 2016-007 Revise Discussion Regarding Location of Steam Leak      24
Detection Temperature Elements
UCR #: 2019-007 Revise MSIV [Main Steam Line Isolation Valve] Position  08/22/2019
Indication Description
Procedures      EN-AA-203-1100  Engineering Evaluations                                13
EN-AA-203-1201  10 CFR Applicability and 5059 Screen Reviews            17
EN-AA-203-1202  10 CFR 5059 Evaluation                                  3
EN-AA-205-1102  Temporary Configuration Changes                        15
Self-Assessments AR 02276319    50.59/Modification Pre-Inspection Assessment            12/02/2019
through
2/06/2019
PDA 19-001      Duane Arnold Nuclear Assessment Report - Engineering    03/28/2019
7
}}
}}

Revision as of 08:35, 27 February 2020

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000331/2019013
ML19345E136
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 12/11/2019
From: Robert Daley
NRC/RGN-III
To: Dean Curtland
Duane Arnold
References
IR 2019013
Download: ML19345E136 (9)
v • d • e


Text

ber 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: DPR-49 Report Number: 05000331/2019013 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 Enclosure

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)

Main article: IP 71111.17

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations CAL-E98-004 Setpoint Calculation High Reactor Vessel Level, HPCI, 2

RCIC, Feedwater, and Turbine Trip in Remote Shutdown -

LS4540

CAL-MC-138 Diesel Oil Storage Tank Level Switch 3

CAL-R17-002 Dose Rate Evaluation of Reactor Vessel Water Levels 0

During Refueling for EAL Thresholds

Corrective Action AR 01988025 NRC CGD [Commercial Grade Dedication] Inspection Issue 06/22/2015

Documents of Third Party Dedication

AR 02100600 NRC Questions on Use of [Recurring-Use Temporary 02/03/2016

Modification] RTM-04-OI151

AR 02102327 2016 50.59: Eval of Portable Heaters During Severe 08/08/2016

Weather

AR 02102503 AOP 903 - Severe Weather 01/14/2016

AR 02102754 2016 50.59: Water Temperature Input to Mark I Analysis 02/22/2016

AR 02103084 2016 50.59: Inspection Identified Inadequate 50.59 01/26/2016

Screening

AR 02115464 RCIC Room Steam Leak Detection Not Consistent with CLB 10/02/2016

[Current Licensing Basis]

AR 02138974 T.S. Bases Change Request: B3.3.6.1 12/14/2016

AR 02138981 UFSAR Change Request: Chapter 7 10/12/2016

AR 02139054 Evaluate Process Utilized to Move STP 3.5.1-03A/B to 09/23/2016

Online

AR 02175375 Power System Stabilizer 50.59 01/18/2017

AR 02332637 2019 NRC 50.59/Mod Pre-Inspection Identified Items 10/24/2019

AR-LIC 2138981 DAEC UFSAR Chapter 7 06/20/2016

PCR 02073808 Annunciator Response Procedure ARP-1C22 40

Hydrogen/Oxygen Control Panel

PCR 02090816 Bases-ATWS (Anticipated Transient Without Scram) 19

PCR 02102503 AOP 903 Severe Weather, Revision 55 01/14/2016

PCR 02225747 AOP 302.1 - Loss of 125 Vdc Power 58

PCR 02259266 Biennial Review - ATWS - RPV Control, 0

PCR 02266292 OI 878.1 - Source Range Neutron Monitoring System 21

Inspection Type Designation Description or Title Revision or

Procedure Date

PCR 02268679 Annunciator Response Procedure ARP 1C22 - 42

Hydrogen/Oxygen Control Panel

PCR 02307806 AOP 302.1 - Loss of 125 Vdc Power 60

Corrective Action AR 02337533 50.59 Screening for EC 290224 12/05/2019

Documents

Resulting from

Inspection

Engineering CA 02102327-01 Placement of Portable Heaters in the MG [Motor Generator] 07/01/2016

Changes Set Room

EC 0000156026 Replace Existing Reactor Feedwater Pumps (RFP) and 43

Motors with RFP and Motors of Larger Capacity

EC 0000283115 FIC2309 Replacement Siemens 353 Controller from Design 1

Level A to B

EC 0000283472 Fukushima Spent Fuel Pool Level Instrumentation 6

EC 0000283785 SBGT 1V-SGT-1A\B Flow Ind Controller Replacement 2

Siemens 353 Controller from Design Level A to B

FIC5828A/B

EC 0000283960 Raise All Level Setpoint for LS3701 to Allow Pump Starts 0

Due to Sticking LE3701 Float at Lowest Level

EC 0000285459 Connect Diesel Air Compressor to Plant Air System 0

EC 0000285499 CAL-E95-015 Calibration Frequency Revision 1

EC 0000285928 PLC 1701C Replacement 1

EC 0000286670 1K001-M Compressor Motor Overload Trip Jumper-ed Out 1

(Bypassed)

EC 0000287838 Revise TE4403 Setpoint on TR4400 to Provide Annunciation 0

with Temperature Rise

EC 0000287965 Disable XR2 Low Oil Level Alarm to Prevent Masking Other 0

Alarms

EC 0000287997 RHR [Residual Heat Removal] Discharge Header Pressure 1

Switch Setpoint

EC 0000288156 TC6924A/B Control Building Chiller Temperature Controller 2

Siemens 353 Controller from Design Level A to B

EC 0000288815 Diesel Air Compressor Back-Up to Plant Air System 0

EC 0000289081 Revise CAL-M91-014 To Be in Compliance with 1

Inspection Type Designation Description or Title Revision or

Procedure Date

ANSI 195-1976, Section 5.4

EC 0000291031 Reconfigure LS2219 Logic to Remove Automatic Opening of 2

SV2219

EC 0000291104 Replace LE-3768 with Longer Length Level Element 3

Engineering ACE 01949946 2016 50.59: Eval of Portable Heaters During Severe 02/16/2016

Evaluations Weather

EC 0000281703 Chromalox Replacement Project 0

EC 0000282458 RWS Cable Replacement 0

EC 0000287931 Implementation of Revised Calculations for LOCA Dose 0

Consequences

Miscellaneous IP 71111.17T Evaluations of Changes, Tests, and Experiments 01/01/2017

NEI 96-07 Guidelines for 10 CFR 50.59 Implementation 1

UCR #: 2016-007 Revise Discussion Regarding Location of Steam Leak 24

Detection Temperature Elements

UCR #: 2019-007 Revise MSIV [Main Steam Line Isolation Valve] Position 08/22/2019

Indication Description

Procedures EN-AA-203-1100 Engineering Evaluations 13

EN-AA-203-1201 10 CFR Applicability and 5059 Screen Reviews 17

EN-AA-203-1202 10 CFR 5059 Evaluation 3

EN-AA-205-1102 Temporary Configuration Changes 15

Self-Assessments AR 02276319 50.59/Modification Pre-Inspection Assessment 12/02/2019

through

2/06/2019

PDA 19-001 Duane Arnold Nuclear Assessment Report - Engineering 03/28/2019

7

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