IR 05000331/2019013: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:ber 11, 2019
{{#Wiki_filter:December 11, 2019


==SUBJECT:==
==SUBJECT:==
Line 31: Line 31:


Sincerely,
Sincerely,
/RA/
/RA/  
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 05000331 License No. DPR-49
 
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety  
 
Docket No. 05000331 License No. DPR-49  


===Enclosure:===
===Enclosure:===
As stated
As stated  


==Inspection Report==
==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
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  


=SUMMARY=
=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.
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.
===List of Findings and Violations===
No findings or violations of more than minor significance were identified.


Additional Tracking Items None.
===Additional Tracking Items===
None.


=INSPECTION SCOPES=
=INSPECTION SCOPES=
Line 54: Line 92:


==REACTOR SAFETY==
==REACTOR SAFETY==
===71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)===
{{IP sample|IP=IP 71111.17|count=28}}


===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.
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
: (1) AR 02175375-01, Power System Stabilizer Removal from Service, January 16, 2017
Line 96: Line 134:
=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


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

Revision as of 09:27, 24 December 2024

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

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:

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

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

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

AR 01988025

NRC CGD [Commercial Grade Dedication] Inspection Issue

of Third Party Dedication

06/22/2015

AR 02100600

NRC Questions on Use of [Recurring-Use Temporary

Modification] RTM-04-OI151

2/03/2016

AR 02102327

2016 50.59: Eval of Portable Heaters During Severe

Weather

08/08/2016

AR 02102503

AOP 903 - Severe Weather

01/14/2016

AR 02102754

2016 50.59: Water Temperature Input to Mark I Analysis

2/22/2016

AR 02103084

2016 50.59: Inspection Identified Inadequate 50.59

Screening

01/26/2016

AR 02115464

RCIC Room Steam Leak Detection Not Consistent with CLB

[Current Licensing Basis]

10/02/2016

AR 02138974

T.S. Bases Change Request: B3.3.6.1

2/14/2016

AR 02138981

UFSAR Change Request: Chapter 7

10/12/2016

AR 02139054

Evaluate Process Utilized to Move STP 3.5.1-03A/B to

Online

09/23/2016

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

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

AR 02337533

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

EC 0000156026

Replace Existing Reactor Feedwater Pumps (RFP) and

Motors with RFP and Motors of Larger Capacity

EC 0000283115

FIC2309 Replacement Siemens 353 Controller from Design

Level A to B

EC 0000283472

Fukushima Spent Fuel Pool Level Instrumentation

EC 0000283785

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

Siemens 353 Controller from Design Level A to B

FIC5828A/B

EC 0000283960

Raise All Level Setpoint for LS3701 to Allow Pump Starts

Due to Sticking LE3701 Float at Lowest Level

EC 0000285459

Connect Diesel Air Compressor to Plant Air System

EC 0000285499

CAL-E95-015 Calibration Frequency Revision

EC 0000285928

PLC 1701C Replacement

EC 0000286670

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

(Bypassed)

EC 0000287838

Revise TE4403 Setpoint on TR4400 to Provide Annunciation

with Temperature Rise

EC 0000287965

Disable XR2 Low Oil Level Alarm to Prevent Masking Other

Alarms

EC 0000287997

RHR [Residual Heat Removal] Discharge Header Pressure

Switch Setpoint

EC 0000288156

TC6924A/B Control Building Chiller Temperature Controller

Siemens 353 Controller from Design Level A to B

EC 0000288815

Diesel Air Compressor Back-Up to Plant Air System

EC 0000289081

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

EC 0000291031

Reconfigure LS2219 Logic to Remove Automatic Opening of

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

Chromalox Replacement Project

EC 0000282458

RWS Cable Replacement

EC 0000287931

Implementation of Revised Calculations for LOCA Dose

Consequences

Miscellaneous

IP 71111.17T

Evaluations of Changes, Tests, and Experiments

01/01/2017

NEI 96-07

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

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

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

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