IR 05000331/2018004

Errata - Duane Arnold Energy Center - NRC Integrated Inspection Report 05000331/2018004

ML19038A277
Person / Time
Site:	Duane Arnold
Issue date:	02/07/2019
From:	Dariusz Szwarc NRC/RGN-III/DRP/B2
To:	Dean Curtland NextEra Energy Duane Arnold
References
IR 2018004
Download: ML19038A277 (14)

Text

UNITED STATES February 7, 2019

SUBJECT:

ERRATA DUANE ARNOLD ENERGY CENTERNRC INTEGRATED INSPECTION REPORT 05000331/2018004

Dear Mr. Curtland:

The U.S. Nuclear Regulatory Commission (NRC) identified an administrative error in NRC Inspection Report 05000331/2018004 January 29, 2019 (ADAMS Accession Number ML19029A443). Specifically, the Section entitled 71114.04Emergency Action Level and Emergency Plan Changes was erroneously omitted from the report. That inspection sample was performed during the time period documented in the report. As a result, the NRC has reissued the report in its entirety with that Section added to correct the error.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Dariusz Szwarc, Acting Chief Branch 2 Division of Reactor Projects Docket No. 50-331 License No. DPR-49

Enclosure:

Inspection Report 05000331/2018004

REGION III==

Docket Number: 50-331 License Number: DPR-49 Report Number: 05000331/2018004 Enterprise Identifier: I-2018-004-0016 Licensee: NextEra Energy Duane Arnold, LLC Facility: Duane Arnold Energy Center Location: Palo, IA Dates: October 1 through December 31, 2018 Inspectors: C. Norton, Senior Resident Inspector J. Beavers, Resident Inspector D. Tesar, Reactor Engineer J. Cassidy, Senior Health Physicist C. Zoia, Senior Operations Engineer G. Hansen, Senior Emergency Preparedness Inspector Approved by: D. Szwarc, Acting Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting an integrated quarterly 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 were identified.

Additional Tracking Items Type Issue Number Title Report Status Section Licensee 05000331/2018-003 Combined Maximum Main 71153 Closed Event Report Steam Line Pathway Leakage Exceeded Technical Specification Limit Licensee 05000331/2018-004 Reactor Protection System 71153 Closed Event Report Actuation

PLANT STATUS

Duane Arnold Energy Center began the inspection period at rated thermal power. On October 19, 2018, the unit scrammed on low reactor water level due to a failed feedwater regulating valve. The scram was without complications. The licensee repaired the feedwater regulating valve, commenced a reactor startup, and synchronized to the grid on October 21, 2018. The unit achieved rated thermal power on October 26, 2018, 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/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 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.

REACTOR SAFETY

71111.01Adverse Weather Protection Seasonal Extreme Weather

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures on November 6, 2018.

71111.04Equipment Alignment Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Reactor Water Cleanup Heat Exchanger Room on October 2, 2018;

(2) 250 Volts Direct Current Power Distribution System on October 12, 2018;

(3) Secondary Containment System on October 19, 2018;

(4) Well Water System on November 14, 2018;

(5) Reactor Protection System on November 16, 2018; and

(6) B Standby Diesel Generator System on November 20, 2018.

71111.05AQFire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) North and South Emergency Response Building 757 on October 31, 2018;

(2) Low Level Radiation Processing Storage Facility on November 7, 2018;

(3) Reactor Building Elevation 757 on November 7, 2018; and

(4) Turbine Building Elevation 780 on November 7, 2018.

71111.06Flood Protection Measures Internal Flooding

The inspectors evaluated internal flooding mitigation protections in the turbine building on November 12, 2018.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Performance

The inspectors observed and evaluated activities associated with a reactor startup following a forced outage on October 21, 2018.

Operator Exams (1 Sample)

The inspectors reviewed and evaluated requalification examination results on December 17, 2018.

71111.12Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Belt replacement on the High Pressure Coolant Injection (HPCI) room exhaust fan on December 7, 2018.

71111.13Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) B Recirculation Motor Generator Scoop Tube Lock Up Troubleshooting on October 2, 2018; and

(2) B Recirculating Pump Speed Regulation on October 9, 2018.

71111.15Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Condition Report (CR) 0223334 B Exhaust Wire Screen was damaged on October 3, 2018.

71111.18Plant Modifications

The inspectors evaluated the following temporary or permanent modifications:

(1) Moisture Separator Drain Tank Level Control on October 4, 2018.

71111.19Post Maintenance Testing

The inspectors evaluated the following post maintenance tests:

(1) Reactor Water Cleanup B Demineralizer Drain Valve on October 18, 2018.

71114.04Emergency Action Level and Emergency Plan Changes

The inspector completed the evaluation of submitted Emergency Action Level and Emergency Plan changes on October 30, 2018. This evaluation does not constitute NRC approval.

RADIATION SAFETY

71124.03In-Plant Airborne Radioactivity Control and Mitigation Self-Contained Breathing Apparatus for Emergency Use

The inspectors evaluated the licensees self-contained breathing apparatus program.

71124.04Occupational Dose Assessment Source Term Characterization

The inspectors evaluated the licensees source term characterization.

External Dosimetry (1 Sample)

The inspectors evaluated the licensees external dosimetry program.

Special Dosimetric Situations (1 Sample)

The inspectors evaluated the licensees performance for special dosimetric situations.

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

(1) MS05: Safety System Functional Failures-1 Sample (October 1, 2017 -

September 30, 2018);

(2) MS09: Residual Heat Removal Systems-1 Sample (October 1, 2017 -

September 30, 2018);

(3) MS10: Cooling Water Support Systems-1 Sample (October 1, 2017 -

September 30, 2018);

(4) BI01: RCS Specific Activity October 2017 through September 2018;

(5) OR01: Occupational Exposure Control Effectiveness October 2017 through September 2018; and

(6) PR01: RETS/ODCM Radiological Effluent Occurrences July 2017 through September 2018.

71152Problem Identification and Resolution Annual Follow-Up of Selected Issues

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Electro Hydraulic Control System Pressure issues on October 25, 2018; and

(2) Feedwater System Digital Controller programming issues on December 6, 2018.

Semiannual Trend Review (1 Sample)

(1) Abnormal reactivity changes on November 27, 2018.

71153Follow-Up of Events and Notices of Enforcement Discretion Licensee Event Reports

The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) Licensee Event Report 05000331/2018-003, Combined Maximum Main Steam Line Pathway Leakage Exceeded Technical Specification Limit, issued on October 22, 2018; and

(2) Licensee Event Report 05000331/2018-004, Reactor Protection System Actuation, issued on December 17,

INSPECTION RESULTS

71153Follow-Up of Events and Notices of Enforcement Discretion Licensee Event Report 2018-003; Combined Maximum Main 71153Follow-Up of Steam Line Pathway Leakage Exceeded Technical Specification Events and Notices of Limit Enforcement Discretion The inspectors reviewed LER 2018-003 that documented failed local leak testing on the main steam line drain path in excess of technical specification limits. The plant was in cold shutdown at the time of discovery, not in a mode of applicability. There were no performance deficiencies associated with the event.

This review closes LER 2018-003.

Licensee Event Report 2018-004; Reactor Protection System 71153Follow-Up of Actuation Events and Notices of Enforcement Discretion The inspectors reviewed LER 2018-004 that documented an uncomplicated SCRAM that occurred October 19, 2018. There were no performance deficiencies associated with the event.

This review closes LER 2018-004.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure. No proprietary information was documented in this report.

• On November 29, 2018, the inspector presented the radiation protection program inspection results to Mr. D. Curtland, Director of Site Operations, and other members of the licensee staff.

• On November 30, 2018, the inspector presented the emergency preparedness program inspection results to Mr. M. Davis, Licensing Manager, and other members of licensee staff.

• On December 18, 2018, the inspector discussed the completed 2018 Licensed Operator Requalification Program annual operating test inspection results with Mr. E. Murray, Operations Training Supervisor.

• On January 3, 2019, the inspectors presented the quarterly integrated inspection results to Mr. P. Hansen, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01Adverse Weather Protection

- 2017 Winter Challenges Lessons Learned

- OP-AA-102-1002; Seasonal Readiness; Revision 28

71111.04Equipment Alignment

- Abnormal Operating Procedure (AOP) 408; Well Water System Abnormal Operation;

Revision 34

- CR 2282032; Steam Coming from PSV271 Reactor Water Cleanup (RWCU) RHX Tube Side

PRV

- OI 324; Standby Diesel Generator System; Revision 123

- OI 324A3; Standby Diesel Generator System Valve Lineup; Revision 15

- OI 358; Reactor Protection System; Revision 70

- OI 388; 250 VDC Power Distribution System; Revision 30

- OI 388A1; 250 VDC Power Distribution System Electrical Lineup; Revision 3

- OI 408; Well Water System; Revision 96

- OI 408A2; Well Water System Valve Lineup; Revision 22

- OI 734; Reactor Building Heating Ventilation Air Conditioning (HVAC) System; Revision 64

OI 734A2; Reactor Building HVAC System Lineup; Revision 1

Operating Instruction (OI) 170; Standby Gas Treatment System; Revision 66

Surveillance Test Procedure NS610001; RWCU System Leakage Inspection Walkdown;

Revision 4

71111.05AQFire Protection Annual/Quarterly

- PFP-LL-757; Pre Fire Plan LLRPSF; Revision 3

- PFP-OC-757; Pre Fire Plan OAG-OCA El. 757; Revision 4

- PFP-RB-757; Pre Fire Plan Reactor Building 757; Revision 4

- PFP-TB-780; Pre Fire Plan Turbine Building 780; Revision 6

71111.06Flood Protection Measures

- AOP 905; Turbine Building Internal Flooding; Revision 3

- Mitigating Strategies Assessments for Hazard Reevaluation; November 2016

- SD-408; Well Water System; Revision 11

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

- AOP 264; Loss of Recirc Pumps; Revision 16

- IPOI 2; Reactor Startup; Revision 164

71111.12Maintenance Effectiveness

- Equipment-Specific Maintenance Procedure; Blower-B515-01; Buffalo Forge Axial Fans;

Revision 5

- Work Order (WO) 40608038; HPCI Room Exhaust Fan

71111.13Maintenance Risk Assessments and Emergent Work Control

- CR 02283080; B Recirc MG Scoop Tube Lock

- CR 02283080; Annunciator 1C04B (C-1) Recirc MG Scoop Tube Lock

- OI 264; Reactor Recirculation System; Revision 133

- OI 264; Reactor Recirculation System; Revision 143

- WO 50502310-01; Replace B Scoop Tub Positioner Pots 90-9201B and 90-9202B

- WO 50502310-09; Lock Scoop Tube Positioner for Potentiometer Change Out

71111.15Operability Determinations and Functionality Assessments

- CR 0223334; B SBDG Exhaust Wire Screen Damaged

71111.18Plant Modifications

- 1.LC-F130-01; Alternate Moisture Separator Drain Tank Level Control; Revision 3

- EN-AA-205-1102; Temporary Configuration Changes; Revision 11

- OI 646; Extraction Steam System; Revision 72

- WO 40625109; 1T92A 2nd State Moisture Separator Drain Tank Level Controller

71111.19Post Maintenance Testing

- CR 2286611; CV2855D Air Line Broke while Clearing Tags

- CR 2286680; RB Equipment Drain Sump Alarm during RWCU Precoat

- WO 40626523-01; RWCU F/D 1T-203B Main Drain Isolation

71114.04Emergency Action Level and Emergency Plan Changes

- Duane Arnold Energy Center Emergency Plan, Section A; Revisions 24 and 25

- Duane Arnold Energy Center Emergency Plan, Section B; Revisions 38 and 39

- Duane Arnold Energy Center Emergency Plan, Section E; Revisions 24 and 25

- Duane Arnold Energy Center Emergency Plan, Section H; Revisions 35 and 36

- Duane Arnold Energy Center Emergency Plan, Appendix 6; Revisions 27 and 28

- EBD F; EAL Bases Document; Revisions 9 and 10

- EPIP Form EAL 01; Emergency Action Level Matrix; Revisions 10 and11

- EP-AA-100-1007; Evaluation of Changes to the Emergency Plan, Supporting Documents and

Equipment (10 CFR 50.54(Q)); Revision 5

- License Amendment No. 301, Renewed Facility Operating License No. DPR-49 MODIFY

THE PLUME EXPOSURE PATHWAY EMERGENCY PLANNING ZONE

- NUC EPR 2001; 10CFR50.54(q) Qualification; Revision 0

- Duane Arnold Energy Center Staff 50.54(q) Reviewer Qualification Records

- PCR 2232471, 2232479, and 2232475; 10 CFR 50.54(q) Screening Form, CMPA 2217817-

Implementation of NRC approved License Amendment Request (LAR) TSCR-165, to change

the southern boundary of the Emergency Planning Zone, Subarea 24 and to update the

Evacuation Time Estimates. Screen; November 16, 2017

- PCR 2202105 and 2202104; 10 CFR 50.54(q) Screening Form, Changes to TSC-01

Emergency Coordinator Checklist, and EOF-07 ER&RD Checklist Screen;

September 14, 2017

- PCR 2227927; CFR 50.54(q) Screening and Evaluation Forms, LAR project for Emergency

Plan Augmentation Times and CMP 2226950 Screen and Evaluation; November 1, 2017

- PCR 2232343, 2236400, and 2232317; 10 CFR 50.54(q) Screen and Evaluation Forms,

EOF Security Access Clerk (EOF-17) Position Specific Checklist, EPIP 1.5 Activation and

Operation of the EOF, and EOF Messenger (EOF-38) Position Specific Checklist Screen and

Evaluation; December 18, 2018

- PCR 2225508; 10 CFR 50.54(q) Screening and Evaluation Forms, EPIP 1.3, Plant Assembly

and Site Evacuation Screen and Evaluation; November 15, 2017

- PCR 2219258; 10 CFR 50.54(q) Screening and Evaluation Forms, EPIP 2.5 Control Room

Emergency Response Organization Screen and Evaluation; August 16, 2017

- PCR 2194687; 10 CFR 50.54(q) Screening Form, Standardization and enhancements of

ERO qualification records through enhancements to EPDM 1009 Screen; October 11, 2017

- PCR 2207827 and 220782; 10 CFR 50.54(q) Screening Form, Revision to NOTE-08 (DAEC

ERO NOTE-08) ERO Notification Web Based Call Out, and Revision to NOTE-01 (DAEC

ERO NOTE-01) ERO Notification - Phone Callout Screen; September 13, 2017

- PCR 2219400, 2219413, 2219411, and 2210582 10 CFR 50.54(q) Screening and Evaluation

Forms, EPIP 2.5, EPIP 1.2, EPIP Form CR-01, EPIP Form CR-06, and EPIP Form

NOTE-07 Screen and Evaluation; August 14, 2017

- PCR 2208971, 2210174, and 2226322; 10 CFR 50.54(q) Screening and Evaluation Forms,

Revisions to EBDF, EPIP 2.2, and EPIP Form EAL 01 Screen and Evaluation;

October 18, 2017

- PCR 2228168 and 223077; 10 CFR 50.54(q) Screening Form, Change to Emergency Plan

and EPIPs 1.2, 1.3, 1.5, 2.1, 2.2, and 4.3 Screen; December 12, 2017

- PCR 2257903; 10 CFR 50.54(q) Screening Form, Revise EPEI Form ERDS-01 Screen;

May 9, 2018

- PCR 2248163; 10 CFR 50.54(q) Screening Revision to EPIP Form MIDAS-01 Screen;

May 8, 2018

- PCR 2257925; 10 CFR 50.54(q) Screening Revision to EPIP Form PAR-01 Screen;

May 30, 2018

- PCR 2218206; 10 CFR 50.54(q) Screening Revision to EPIP Form TSC-04 Screen;

January 26,2018

- PCR 2237711; 10 CFR 50.54(q) Screening Revision to EPIP Form TSC-01 Screen;

February 13, 2018

- PCR 2247222 and 2242901; 10 CFR 50.54(q) Screening Revision to EPIP Form OSC-03

Screen; February 13, 2018

- PCR 2245898; 10 CFR 50.54(q) Screening Revision to EPIP Forms TSC-6, TSC-37, and

TSC-42 Screen; February 13, 2018

- EC 285074; 10 CFR 50.54(q) Screening Replacement of TSC Diesel Generator Screen;

April 11, 2018

- PCR 2227234; 10 CFR 50.54(q) Screening Revision to EPIP Form EOF-07 Screen;

January 24, 2018

- PCR 2257913; 10 CFR 50.54(q) Screening Revision to EPIP Form TSC-07 Screen;

April 25, 2018

- PCR 2257897; 10 CFR 50.54(q) Screening Revision to EPIP Form TSC-39 Screen;

April 25, 2018

- AR 02215634; Fleet EP Review of 50.54 Q Evaluations not Documented

71124.03In-Plant Airborne Radioactivity Control and Mitigation

- ACP 1411.20; Respiratory Protection; Revision 41

- CR 2292366; Procedure Change Request; Add the NIOSH Graphic Showing Types/Styles of

Facial Hair that Negatively Impact Respirator Sealing Surfaces to ACP 1411.20 - Respiratory

Protection; November 28, 2018

- CR 2292369; Procedure Change Request; Add the NIOSH Graphic Showing Types/Styles of

Facial Hair that Negatively Impact Respirator Sealing Surfaces to HPP 3109.84 - Operation

of the Respirator Fit Test Equipment; November 28, 2018

- HPP 3106.03; Description and Issuance of Respiratory Protection Equipment; Revision 20

- HPP 3106.04; Inspection, Maintenance and Quality Assurance of Respiratory Protection

Equipment; Revision 39

- Posi3 USB Test Results; Complete SCBA Test; Duane Arnold 21; August 15, 2017

- Posi3 USB Test Results; Complete SCBA Test; Duane Arnold 21; August 14, 2018

- Posi3 USB Test Results; Complete SCBA Test; Duane Arnold 22; August 15, 2017

- Posi3 USB Test Results; Complete SCBA Test; Duane Arnold 22; August 14, 2018

- Posi3 USB Test Results; Complete SCBA Test; Duane Arnold 24; August 15, 2017

- Posi3 USB Test Results; Complete SCBA Test; Duane Arnold 24; August 14, 2018

71124.04Occupational Dose Assessment

- Certificate of Accreditation to ISO/IEC 17025:2005; NVLAP Lab Code 100555-0; Mirion

Technologies (GDS); July 1, 2017 through June 30, 2018

- Certification of Accreditation to ISO/IEC 17025:2005; NVLAP Lab Code 100555-0; Mirion

Technologies (GDS); July 1, 2018 through June 30, 2019

- CR 2292659; Determine the Adequacy of Internal Dose Calculations, RFO 28;

November 19, 2018

- HPP 3104.02; Personnel Contamination Monitoring, Whole Body Counting and

Decontamination; Revision 50

- HPP 3105.02; Exposure Evaluation, Investigation, and Reporting; Revision 28

- HPP 3105.05; Administration of In-Vivo and In-Vitro Bioassay; Revision 28

- Radiological Engineering Calculation 02-001-A; Periodic Evaluation of the Passive Internal

Monitoring Program at the Duane Arnold Energy Center; June 4, 2002

- RP-AA-100; Radiation Protection Administrative Program; Revision 8

- RP-AA-101; Personnel Monitoring Program; Revision 4

- RP-AA-101-1001; Personnel Monitoring Device Issue; Revision 3

- RP-AA-101-2004; Method for Monitoring and Assigning Effective Dose Equivalent for High

Gradient Work; Revision 7

- RPM 01/2003; Prospective Evaluation; Revision 4

71151Performance Indicator Verification

- ACP 1402.4; NRC, WANO, & MOPR Performance Indicator Reporting; Revision 22

- ACP 1402.4; NRC, WANO, & MOPR Performance Indicator Reporting; Revision 22

- LI-AA-100-10003; NRC Performance Indicator; Revision 1

- LI-AA-100-10003; NRC Performance Indicator; Revision 1

- Maintenanced Rule Data Entry Sheets; October, 2017 through September 2018

- Reactor Oversight Process: NRC PI Data Calculation, Review and Approval; RCS Activity

(RCSA); Various Dates

- Reactor Oversight Process: NRC PI Data Calculation, Review and Approval; Occupational

Exposure Effectiveness; Various Dates

- Reactor Oversight Process: NRC PI Data Calculation, Review and Approval; RCS Activity

(RCSA); Various Dates

- Reactor Oversight Process: NRC PI Data Calculation, Review and Approval; Occupational

Exposure Effectiveness; Various Dates

- Reactor Oversight Process: NRC PI Data Calculation; RETS/ODCM Radiological Effluent;

Various Dates

- Reactor Oversight Process: NRC PI Data Calculation; RETS/ODCM Radiological Effluent;

Various Dates

71152Problem Identification and Resolution

- AOP 255.2; Power/Reactivity Abnormal Change; Revision 48

- CR 2267942; Moisture Separator Drain Tank Controller Malfunction

- CR 2272128; Feedwater Level Controller Malfunction

- CR 2280982; 1F-51D, Charge Pump B Filter Change

- CR 2281086; EHC Pressure Dropping Low on Turbine Reset

- CR 2281097; Main Turbine did not Trip with Fuses Pulled

- CR 2281206; PS3672B, EHC Pump B Low Pressure Auto Start Calibration

- CR 2283080; Scoop Tube Positioner Malfunction

- CR 2283317; Moisture Separator Drain Tank Controller Malfunction

- CR 2283744; P13699B, EHC Pump B Discharge Pressure Indicator High

- CR 2284915; Moisture Separator Drain Tank Valve Malfunction

- CR 2287024; ZC1579 Controller Programming

- CR 2287622; EHC Pressure Fluctuating Below Normal Rated Power

- CR 2288859; RFO 26 AOV Review

- CR 2288989; EHC Header Discharge Pressure Lowered during Load Line Adjustment

- CR 2289116; Work Quality

- CR 2883316; ZC1611 Controller Programming

- Drawing 234T849; Turbine Control Diagram; Revision 21

- WO 40585866; IT042B; B EHC Accumulator N2 Pressure

- WO 40605927; IT042A; A EHC Accumulator N2 Pressure

71153Follow-Up of Events and Notices of Enforcement Discretion

- AOP 264; Loss of Recirc Pumps; Revision 017

- Corrective Action Program Review; December 19, 2018

- CR 2256885; Automatic Reactor Scram due to B Feed Regulating Valve Failure

- CR 2279568; MO4423 Failed LLRT Testing

- CR 2279621; MO4423 Failed LLRT Testing Reportability

- EOP-1; RPV Level Control

- ER 2279568-04; Equipment Failure Investigation Checklist; Revision 13

- Event Notification 53676

- LER 2018-003; October 22, 2018

- LER 2018-004; December 19, 2018

- Organizational Effectiveness Investigation; MO4423 Failure

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