IR 05000346/2020001

Integrated Inspection Report 05000346/2020001

ML20139A017
Person / Time
Site:	Davis Besse
Issue date:	05/15/2020
From:	Billy Dickson NRC/RGN-III
To:	Bezilla M Energy Harbor Nuclear Corp
References
IR 2020001
Download: ML20139A017 (23)

Text

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2020001

Dear Mr. Bezilla:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On April 20, 2020, the NRC inspectors 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/

Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects Docket No. 05000346 License No. NPF-3

Enclosure:

As stated

Inspection Report

Docket Number: 05000346 License Number: NPF-3 Report Number: 05000346/2020001 Enterprise Identifier: I-2020-001-0044 Licensee: Energy Harbor Nuclear Corp.

Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Inspection Dates: January 01, 2020 to March 31, 2020 Inspectors: S. Bell, Health Physicist E. Fernandez, Reactor Inspector J. Harvey, Resident Inspector D. Mills, Senior Resident Inspector C. Norton, Senior Resident Inspector J. Park, Reactor Inspector J. Rutkowski, Project Engineer Approved By: Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Davis-Besse Nuclear Power Station, 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.

PLANT STATUS

The plant began the inspection period at rated thermal power. On January 16, 2020, the plant started coasting down with periodic power reductions. The licensee shut down the plant for the refueling outage on February 29, 2020. The plant remained shut down for 25 days. On March 24, 2020, the licensee started up the plant, but operators tripped the plant at very low power on March 25, 2020, due to a failed transformer fuse. The licensee restarted the plant on March 26, 2020, and the plant reached rated thermal power on March 30, 2020. The plant remained at or near full power for the rest of the inspection period.

On February 27, 2020, the licensees parent company successfully completed its Chapter 11 restructuring process and emerged from bankruptcy as Energy Harbor Nuclear Corp. The NRC Region III inspectors used flexibility in the baseline inspection program to assess the potential impact of the financial conditions on licensee performance. Through February 27, 2020, the inspectors applied additional focus to the following areas:

(1) impact on regulatory required plant staffing,

(2) corrective maintenance backlog,

(3) changes to the planned maintenance schedule,

(4) corrective action program implementation, and

(5) reduction in outage scope, including risk-significant modifications. No concerns were identified.

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/readingrm/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. From January 1 - March 19, 2020, 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Decay heat/low pressure injection (DH/LPI) train 2 while DH/LPI train 1 was out of service for planned emergency core cooling system room cooler maintenance during the week ending January 11, 2020

(2) Emergency diesel generator (EDG) train 2 while component cooling water train 1 was out of service for planned testing during the week ending February 1, 2020

(3) High pressure injection train 1 while DH/LPI train 2 was out of service for planned maintenance and EDG 2 was out of service for planned testing during the week ending February 22, 2020

(4) Decay heat/low pressure injection train 1 while DH/LPI train 2 was in operation during the planned reactor drain down during the week ending March 7, 2020

(5) Decay heat/low pressure injection train 2 while defueled and credited as an alternate means of spent fuel pool cooling during the week ending March 14, 2020

71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Electrical penetration room 2, fire area DF, during the week ending February 8, 2020

(2) East and southwest penetration areas of the annulus, fire areas A and AB, during the week ending March 21, 2020

(3) High voltage switchgear room A, fire area S, during the week ending April 4, 2020

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from March 2nd, 2020 to March 13th, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

• Ultrasonic Examination (UT) of 2.5 Elbow to Pipe Weld for High Pressure Injection Emergency Core Cooling, Component ID HP-33C-CCB-2-35-SWE

• Liquid Penetrant Examination (PT) of the 8.25 SG 1 Upper Primary Head Nozzle Head Vent Safe-End Weld Component ID RC-SG-1-2-W253

• Inservice Inspection (ISI) Report 21-PT-030 Non-Relevant Indication (<1/16")

on Upper Primary Head Nozzle Head Vent Safe-End Weld Component ID RC-SG-1-2-W253

• Work Order (WO) 200744645-01 2 1/2" HP2A Valve Replacement 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

• UT of 69 penetrations on the Reactor Vessel Closure Head (RVCH)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

• CR-2019-02550 Decay Heat and Low-Pressure Injection DH Pumps Test Line Relief DH2761

• CR-2020-00129 Emergency Sump, Borated Water Storage Tank Isolation Valve DH7A

• CR-2019-06622 Containment Spray Discharge CS26 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.

• Eddy current testing of 15604 Tubes in steam generator (SG 1B) and 15580 Tubes in SG 2A

• Secondary side visual examinations of SG 1B and SG 2A to Inspect Tie Rod Bowing and Tube Bowing

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1) The inspectors observed and evaluated licensed operator performance in the control room during the shutdown for the planned refueling outage during the week ending February 29, 2020, and the plant trip recovery during the week ending March 28, 2020 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) Licensed operator requalification simulator scenario on February 11, 2020

71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Structures monitoring and aging management associated with pipe supports

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) Component cooling water pump 1 pump bearing replacement, constant level oiler installation, and new pump bearing oil seal installation

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Planned replacement of integrated control system modules and delta Tcold adjustment during the week ending January 11, 2020

(2) Emergent issue during nuclear instrument calibration resulting in unplanned power change during the week ending January 18, 2020

(3) Planned maintenance on component cooling water train 1 during the week ending January 25, 2020

(4) Emergent work on the seal oil vacuum pump and planned orange risk to personal safety (confined space activity) during the week ending February 8, 2020

(5) Planned maintenance on decay heat/low pressure injection 2 pump resulting in an orange risk to nuclear generation window during the week ending February 22, 2020

(6) Emergent conflict between high pressure injection system maintenance work and the reactor coolant system drain down contingency plan during the week ending March 7, 2020

(7) Yellow shutdown defense-in-depth risk window for reactor coolant system reduced inventory and steam generator nozzle dam installation during the week ending March 7, 2020

(8) Heavy lift associated with the reactor head removal and movement to head stand during the week ending March 7, 2020

(9) Planned fuel movement and defueled activities during the week ending March 14, 2020

(10) Yellow shutdown defense-in-depth risk window for planned reactor coolant drain following core reload during the week ending March 21, 2020

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Condition Report (CR) 2019-10096: Bolt found missing in diesel fuel oil pressure relief valve DO3672

(2) CR 2020-01984: 1R21 Framatome - Potentially incorrect CRDM [control rod drive mechanism] o-ring lubricant supplied as equivalent

(3) CR 2020-01840: Transverse crack in peripheral weld AFPT [auxiliary feedwater pump turbine] #2 governor

(4) CR 2020-02064: CF [core flood] 1544 LLRT [local leak rate test] exceeded its MALR

[maximum allowable leakage rate]

(5) CR 2020-01702: Rust and staining on reactor vessel closure head flange

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

(1) ECP 16-0332-001, Emergency feedwater (EFW) NFPA 805 manual isolation circuit

(2) ECP 19-0011-004, Replacement of RCP [reactor coolant pump] seal return flow instrumentation

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) Auxiliary feedwater pump 1 after planned maintenance during the week ending January 4, 2020

(2) Component cooling water pump 1 following planned maintenance during the week ending February 1, 2020

(3) Decay heat/low pressure injection train 2 following planned maintenance during the week ending February 22, 2020

(4) Startup transformer X02 following tap changes during the week ending March 7, 2020

(5) High pressure injection 2A following planned maintenance during the week ending March 7, 2020

(6) Emergency diesel generator 1 governor testing and tuning following planned governor replacement during the week ending March 14, 2020

(7) Zero power physics testing during the week ending March 28, 2020

==71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated licensee activities during refueling outage 21 from February 28, 2020 to March 30, 2020

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)==

(1) Auxiliary feedwater pump 2 quarterly surveillance during the week ending February 15, 2020

(2) Spent fuel pool ventilation system refueling interval test during the week ending March 7, 2020

(3) Safety features actuation system train 2 integrated test during the week ending March 7, 2020

(4) Off-Site AC sources train B bus transfer test during the week ending March 14, 2020

(5) Emergency diesel generator 2 monthly surveillance run during the week ending March 14,

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 03.01)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated radiological protection-related instructions to plant workers Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material:

(1) Observed licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA)

(2) Observed licensee contamination surveys during steam generator work activities Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities:

(1) Steam Generation Nozzle Dam Installation under RWP 120-5301

(2) Auxiliary Building Radiological Controls for Radiography under RWP 120-6052

(3) HP2A (high pressure injection line 2-1 isolation) Valve Replacement under RWP 120-6053 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Auxiliary Building for Radiography

(2) Containment 603' Elevation Refueling Floor Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements

71124.02 - Occupational ALARA Planning and Controls Implementation of ALARA and Radiological Work Controls (IP Section 03.03)

The inspectors evaluated the licensees communication of as low as is reasonably achievable ALARA and radiological work controls for the following work activities:

(1) Steam Generation Nozzle Dam Installation under RWP120-5301

(2) HP2A (high pressure injection line 2-1 isolation). Valve Replacement under RWP 120-6053

Radiation Worker Performance (IP Section 03.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance during:

(1) The inspectors evaluated the implementation of as low as is reasonably achievable techniques for work activities during the 1R21 refueling outage

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

(1) Unit 1 (January 2019 - December 2019)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)

(1 Sample)

(1) Unit 1 ( January 2019 - December 2019)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

(1) Unit 1 (January 2019 - December 2019)

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

Trend of Work Planning and Work Management issues

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in work management that might be indicative of a more significant safety issue

71153 - Follow-up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)

(1) The inspectors evaluated the plant trip during start-up due to a failed Potential Transformer (PT) fuse and licensees performance on March 25,

INSPECTION RESULTS

Observation: Trend of Work Planning and Work Management issues 71152 The inspectors reviewed the licensees corrective action program for potential adverse trends in work planning and work management that might be indicative of a more significant safety issue. During the review period for this inspection sample, the inspectors noted that a significant number of low-level performance issues and errors had challenged the licensee.

The inspectors determined that though some of these issues were directly attributable to human performance and/or procedural compliance, there were several that could be attributed to work planning and work management deficiencies. Specific examples associated with this trend included, but were not limited to:

• During the third quarter of 2019, the licensee commenced work to replace the control room emergency air temperature control system train 2 compressor. The plant risk due to the work was modeled as green but when maintenance personnel went out into the field, they identified the lift path for the train 2 compressor required lifting it over the train 1 equipment.

The personnel correctly identified that this situation significantly increased the nuclear safety and generation risk (to yellow) and stopped work. The inspectors noted that the work planning process could have identified this issue prior to work starting. (CR 2019-06415)

• While performing a field walkdown for motor driven feedwater pump target rock cable replacement, the licensee recognized that the conduit intended for use had other safety-related cables running through it that had not been identified during preparation of the engineering change package and work order. The licensee halted the work and developed an alternate approach. The inspectors determined that if this condition had not been recognized and work had proceeded as originally planned, the risk could have been higher than expected. Additionally, the inspectors noted this issue could have been identified during the engineering change process or the work planning process. (CR 2019-06418)

• During a post maintenance run of the emergency feedwater pump, the work order mistakenly directed operators to run the emergency feedwater pump with valves aligned for steam generator injection and not recirculation as intended. The error resulted in an unintended emergency feedwater pump injection into Steam Generator 1 (SG1) for one minute and seventeen seconds. The inspectors noted this event could have been avoided at multiple points during the work planning process and execution of the work order. The inspectors documented this issue in inspection report 2019004 (section 71152).

(CR 2019-07705)

• During a scheduled functional test of the train 2 containment normal range radiation monitor (RE4597BA), the operator performing the test was provided the procedure written for the train 1 containment normal range radiation monitor (RE4597AA). The operator followed the procedure he was given and initiated work on the wrong train component rendering both trains inoperable. The inspectors documented this issue in inspection report 2019002 (section 71152). (CR 2019-03346)

Individually, none of these examples may suggest an ongoing problem but when viewed in the aggregate, the inspectors determined they may indicate a programmatic weakness.

Specifically, for these and other work planning deficiencies the station may be missing the opportunity to identify and resolve deficiencies prior to the work being started, potentially resulting in an adverse impact to the plant. The inspectors provided these observations to the licensee and the licensee agreed that additional focus may be necessary to evaluate the trend. The NRC inspectors plan to continue monitoring the licensees actions to address work planning and work management issues.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On April 20, 2020, the inspectors presented the integrated inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff.

• On March 6, 2020, the inspectors presented the radiation protection baseline inspection results to Mr. G. Norlund, Radiation Protection Manager, and other members of the licensee staff.

• On March 25, 2020, the inspectors presented the Davis-Besse ISI Inspection results to Mr. P. McCloskey, Performance Improvement Director, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action CR-2019-02774 DHP#2 Suction Pressure Gauge Out of Cal 03/25/2019

Documents CR-2019-07307 Oil Drop Found on LPI Pump 2 Inboard Bearing 09/03/2019

Drawings M-033A High Pressure Injection 49

M-033B Decay Heat Train 1 60

M-033C Decay Heat Train 2 30

M-035 Spent Fuel Pool Cooling System 59

Procedures DB-OP-06011 High Pressure Injection System 34

DB-OP-06012 Decay Heat and Low-Pressure Injection Operating 75

Procedure

DB-OP-06316 Diesel Generator Operating Procedure 63

Work Orders 200728759 DB-SP3447-001 - Decay Heat Train 2 Pump and Valve Test 09/24/2019

71111.05 Fire Plans PFP-AB-325 High Voltage Switchgear Room A 05

PFP-CB-A236H Annulus Space Except East and Southwest Penetration 07

Areas at Elevations 585 and 603

PFP-CB-A236L East Penetration Area of Annulus Space Elevations 585 and 04

603

Miscellaneous Fire Hazards Analysis Report 28

Procedures DB-FP-04014 Fire Hose Station Inspections 11

71111.08P Corrective Action CR-2020-01702 Rust Deposits and Staining Noted on RVCH Fange 03/20/2020

Documents CR-2020-01798 New Indication Type Identified During SG Tube Examination 03/04/2020

Resulting from CR-2020-02164 Non-Relevant Indications Observed on Nine Nozzles During 03/12/2020

Inspection RVCH UT Exams

Procedures 0280-TECR- EPRI Appendix H/N Eddy Current Technique Validation 00

104262

54-ISI-240-048 Visible Solvent Removable Liquid Penetrant Examination 05/24/2019

Procedure

54-ISI-603-011 Automated Ultrasonic Examination of RPV Closure Head 02/24/2020

Penetrations Containing Thermal Sleeves

54-ISI-829-014 PDI Generic Procedure for the Ultrasonic Examination of 01/22/2020

Dissimilar Metal Welds PDI-UT-10

54-ISI-836-018 PDI Generic Procedure for Ultrasonic Examination of 01/22/2020

Austenitic Piping Welds PDI-UT-2

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 200744645-01 Davis-Besse 2 1/2 HPA Valve Replacement 02/17/2019

71111.11Q Miscellaneous Simulator Guide CYC 2020-01

Procedures DB-OP-02528 Instrument Air System Malfunctions 26

NOP-OP-1002 Conduct of Operations 14

71111.12 Corrective Action CR-2019-10259 CCW Pump Outboard Bearing Design 12/09/2019

Documents CR-2020-00174 Component Cooling Water Pump #1 Mechanical Seal Leak 01/10/2020

CR-2020-00362 Design Engineering Review/Evaluation of Data for any 01/17/2020

Impact on Design Basis of CCW Pump 1

CR-2020-00365 Abnormal Color in Oil Sample from CCW Pump 1 Outboard 01/18/2020

Bearing

CR-2020-00642 Design Engineering Evaluation of CCW Pump 1 01/27/2020

Performance per DB-PF-03572, Step 4.41

CR-2020-00651 CC1 (CCW Pump 1 Suction Valve) Stem Lock Handle is 01/27/2020

Missing

CR-2020-01257 CCW Pump #1 Lessons Learned 02/18/2020

CR-2020-02239 Change oil in P43-1 as Soon as Practical Due to High Iron 03/15/2020

and Silicon

CR-2020-10256 CCW Pump Inboard and Outboard Bearing Reservoir 12/09/2019

Coatings are Deteriorating

Corrective Action CR-2020-02858 Rust Identified on Spring Can Pipe Support 33-GCB-1-H3 04/01/2020

Documents

Resulting from

Inspection

Miscellaneous Structures Monitoring Inspection ECCS Pump Rm 1 03/31/2017

Structures Monitoring Inspection ECCS Pump Rm 1 08/16/2019

Structures Monitoring Inspection ECCS Pump Rm 2 03/13/2017

LRPD-05 Aging Management Program Evaluation Results - Structures 5

3.7 Monitoring Program

MRPM Maintenance Rule Program Manual 37

NDE Reports 20-VT-101 Section XI Variable Spring Hanger Support Aux/Rm 500 03/10/2018

20-VT-108 Section XI Variable Spring Support AFP #1 Rm 03/13/2018

Procedures DB-PF-03572 Component Cooling Water Pump 1 Baseline Test 06

DBBP-OPS-0011 Protected Equipment Posting 14

Inspection Type Designation Description or Title Revision or

Procedure Date

EN-DP-01511 Structures Monitoring 11

NA-QC-05560 Visual Examination Procedure for VT-1, VT-3, and General 12

Visual Examinations

Work Orders 200708089 Repair Inboard Bearing Oil Leak 03/19/2020

200736805 CCW Pump 1 Clean/Lubricate/Inspect 03/18/2020

200739481 CCW Pump1 Oil Level Validation 03/23/2020

200763444 CCW Pump 1 Constant Level Oilers 01/29/2020

71111.13 Corrective Action CR 2017-10941 Pipe Spring Identified on the Separator Tank for the Seal Oil 10/31/2017

Documents Vacuum Pump (P76_H)

CR 2020-00607 Main Gen Seal Oil Vacuum Pump Degraded 01/25/2020

CR-2020-00230 Power Excursion While Placing ICS Back in Auto 01/13/2020

CR-2020-01255 As Found Condition Identified with the New Seal Cartridge 02/17/2020

for the Decay Heat Pump

CR-2020-01257 CCW Pump #1 Lessons Learned 02/18/2020

CR-2020-01363 Decay Heat Pump 2 Inboard Seal Package Leakage ~2 dpm 02/21/2020

CR-2020-01622 ICS11A Failed to Operate from Control Room During Plant 03/01/2020

Shutdown

CR-2020-01848 1R21 Framatome - Nuclear Instrument (NI) Well Covers 03/05/2020

Leaking

Drawings M-035 Spent Fuel Pool Cooling System 59

OS-025 Main Generator Seal Oil System 14

Miscellaneous Response to Generic Letter Number 88-17, Loss of Decay 01/03/1989

Heat Removal

Acuren Radiography Shot Plan for HP2A at DBNPS 3

1R21 Shutdown Contingency Plan for RCS Drain Below Flange Level and 0

Defense In Depth Operation Below 80 Inches Above the RCS Hot Leg

Report Centerline

Lesson Plan G- G-OPS-FHT Operations and Operation Contract Support 7

OPS-FHT Personnel Fuel Handling Equipment

NOBP-OP-0007- 1R21 Reactor Head Lifts From and to the Reactor Vessel 02/10/2020

IPTE

Worksheet

NOP-CC-5703-05 Repair/Replacement Certification Record 04

NOP-OP-1007-01 Risk Management Plan 7

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures DB-MM-09088 Reactor Vessel Head Removal 10

DB-MM-09089 Reactor Vessel Closure Head Stud Removal 09

DB-MM-09388 Reactor Vessel Head CRDM Service Structure Disconnects 01

DB-MN-00006 Control of Lifting and Handling of Heavy Loads 17

DB-OP-02016 Generator Alarm Panel 16 Annunciators 31

DB-OP-02527 Loss of Decay Heat Removal 20

DB-OP-06002 RCS Draining and Nitrogen Blanketing 28

DB-OP-06902 Power Operations 68

DBBP-OPS-0011 Protected Equipment Posting 14

NOBP-OP-0007 Conduct of Infrequently Performed Tests or Evolutions 7

NOP-OP-2018-02 Report of Repair/Replacement Activities for Nuclear 03

Facilities

Work Orders 200755711 Decay Heat and Low Pressure Injection Install Cartridge 03/12/2020

Seals

71111.15 Corrective Action 2019-00351 Info Only Test on Relief Valve DO3671. Valve did not Lift 01/14/2019

Documents 2019-10096 Bolt Found Missing in Diesel Relief Valve DO3672 12/03/2019

20-01840 Transverse Crack in Peripheral Weld AFPT #2 Governor 03/05/2020

20-02064 CF1544 LLRT Exceeded Its MALR 03/10/2020

CR 2020-01984 1R21 Framatome - Potentially Incorrect CRDM [Control Rod 03/09/2020

Drive Mechanism] O-Ring Lubricant Supplied as Equivalent

CR-2020-01257 CCW Pump #1 Lessons Learned 02/18/2020

CR-2020-01702 Rust and Staining on Reactor Vessel Closure Head Flange 03/02/2020

CR-2020-01798 New Indication Type Identified during SG Tube Examination 03/04/2020

CR-2020-01840 Transverse Crack in Peripheral Weld AFPT #2 Governor 03/05/2020

CR-2020-01925 Nuclear Fuel - DB1R21: Fuel Inspection - Fuel to Baffle 03/07/2020

Interaction Fuel Rod Wear Observed on Fuel Assembly

CR-2020-01936 DB-ZS-ICS-11B-B1 Position Switch for PV-ICS11B Not 03/08/2020

Charging

CR-2020-01992 White Fibrous Material Identified on the Top Side of RVCH 03/09/2020

CRDM Nozzle 23

Drawings DB-MM-09190 Control Rod Drive Mechanism Quick Vent and Hydraulic 14

Inspection Type Designation Description or Title Revision or

Procedure Date

Closure Maintenance

OS-041C Emergency Diesel Generator Diesel Oil System 19

Engineering 601154925 Evaluate ICS38A Seat Seal Weld Crack 03/11/2018

Evaluations

Miscellaneous ISTB4 Pump and Valve Basis Document, Volume IV - Maximum 23

Allowable Leakage Rate (MALR) Basis

Procedures DB-MM-09344 Emergency and Station Blackout Diesel Engine 4-Year 07

Maintenance

DB-OP-06012 Decay Heat and Low Pressure Injection System Operating 75

Procedure

DB-OP-06234 Emergency Feedwater System 06

NOP-LP-2018-02 Report of Repair/Replacement Activities for Nuclear 03

Facilities

NOP-OP-1009 Operability Determinations and Functionality Assessments 08

Shipping Records Purchase Order Quality Control Receiving Inspection Report for DC Fuel Oil 05/08/2012

45382204/0 Pump

Purchase Order Quality Control Receiving Inspection Report for Valve - 06/12/2015

45463301/1 Relief from Supplier Engine Systems Incorporated

71111.18 Engineering 16-0332 Emergency Feedwater (EFW) NFPA Manual Initiation Circuit 1

Changes 19-0011-004 Replacement of RCP Seal Return Flow Instrumentation - 3

FEMU60D/FTMU60D (and Installation of Relief Valve to

Address Potential Overpressurization of Penetration 56

Piping)

71111.19 Corrective Action CR 2020-02613 ZPPT: Cycle 22 Control Rod Worth Greater than Predicted 03/25/2020

Documents CR 2020-02682 Cycle 22 Hot Zero Power (HZP) Reactivity Anomaly Larger 03/27/2020

than Expected

CR-2020-01245 Voided Pipe Upstream of DH200 02/17/2020

CR-2020-01257 CCW Pump #1 Lessons Learned 02/18/2020

CR-2020-01363 Decay Heat Pump 2 Inboard Seal Package Leakage ~2 dpm 02/21/2020

CR-2020-01891 HP2A Stroke Times are Less Than Expected Stroke Times 03/06/2020

CR-2020-01895 HPI Pump 2-D Horizontal Vibe Reading in the Alert Range 03/07/2020

DB-SP-03151 AFP 1 Quarterly Test 29

Miscellaneous NOP-CC-5703-05 Repair/Replacement Certification Record 04

Procedures DB-ME-09700 Woodward 2301A Electronic Load Sharing and Speed 5

Inspection Type Designation Description or Title Revision or

Procedure Date

Control Setup and Adjustment

DB-MM-09098 AFPT Governor Maintenance 17

DB-MM-09150 AFPT Maintenance 17

DB-OP-06314 13.8 KV Switching 17

DB-OP-06316 Diesel Generator Operating Procedure 3

DB-PF-03207 HPI Pump Comprehensive and Check Valve Forward Flow 12

Test Train 1

DB-PF-03208 HPI Pump Comprehensive and Check Valve Forward Flow 13

Test Train 2

DB-PF-03572 Component Cooling Water Pump 1 Baseline Test 06

DB-PF-09302 Testing Motor Operated Valves 10

NOP-LP-2018-02 Report of Repair/Replacement Activities for Nuclear 03

Facilities

Work Orders 200738187 AFP 1 Quarterly Test 01/02/2020

200746960 Auxiliary Feedwater Pump Turbine 1-1 Preventive 01/02/2020

Maintenance

200755827 NE3212-001 Zero Power Physics Test RFL 03/25/2020

200755962 HPI Pump Comprehensive Test 03/07/2020

71111.20 Corrective Action 2020-02269 TYTRC7A [Reactor Coolant Loop 2 Temperature Difference 03/16/2020

Documents Indicator] Found Out of Tolerance

CR-2020-00683 Procedure Non-compliance: NOP-LP-4011 - Work Hour 01/29/2020

Controls

CR-2020-00984 Cycle 22 Fuel Receipt - Marking Identified on Fuel Cladding 02/08/2020

of Assembly UDDG65 During Receipt Inspection

CR-2020-01190 Pipe Supports Removed During MFPT #2 Pre-Outage Work 02/14/2020

CR-2020-01617 DB-PF-03180 Leakage Observed from RC 51 02/29/2020

CR-2020-01758 1R21 Framatome Spring Scale Not Used for CRDM 03/04/2020

Leadscrew Uncoupling Parking

CR-2020-01863 Cooling Tower Column Degradation 03/06/2020

CR-2020-01880 HP2A Critical Path Re-Assembly Delays 03/06/2020

CR-2020-01886 Rust Buildup Found on Internals of New Aux Feed Trip 03/06/2020

Throttle Valve

CR-2020-01897 Ground on Bus E1 03/07/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-2020-01904 Corrosion Found on Shield Building Wall 03/07/2020

CR-2020-02009 1R21 - Incidental Duties Performed Off-site Result in Fatigue 03/09/2020

Rule Violations

CR-2020-02112 DB 1R21 Trend in Work Hour Rule Compliance 03/11/2020

CR-2020-02112 DB 1R21 Trend in Work Hour Control Compliance 03/11/2020

CR-2020-02164 Non-Relevant Indications Observed on Nine Nozzles During 03/12/2020

RVCH UT Exams

CR-2020-02203 Emergency Diesel Generator 1 Emergency Shutdown 03/13/2020

CR-2020-02217 SP7A 3-way Valve Vent Hole is Leaking 03/14/2020

CR-2020-02222 Diode for K2 Relay Shorted 03/14/2020

CR-2020-02238 Issue Noted During Performance of DB-MI-03743 03/15/2020

CR-2020-02248 ICS11A Did Not Operate Smoothly 03/15/2020

CR-2020-02448 1R21 CTMT Closeout Inspection Results 03/20/2020

CR-2020-02524 1R21 - Unapproved Material Found in CTMT During Mode 3 03/23/2020

CR-2020-02557 Foreign Material Identified During Mode 3 Inspection of 03/24/2020

Integrated Head Assembly

CR-2020-02562 1R21 BACC: A Packing and Pipe Cap Leak Was Found on 03/24/2020

CF60

CR-2020-02576 1R21 Final CTMT Closeout Inspection Results 03/24/2020

Corrective Action CR-2020-01376 Fuel Handling JFG Documentation Issue 02/21/2020

Documents CR-2020-01650 Material Control Within a Posted Protected Equipment Area 03/01/2020

Resulting from CR-2020-02063 1R21 Framatome - Spent Fuel Building FME Area Sign 03/10/2020

Inspection

Miscellaneous NOBP-OP-1004- Evolution Specific Reactivity Plan 1/7/2020

Procedures Cycle 22 COLR Cycle 22 Core Operating Limits Report 1

DB-MM-09234 Equipment Hatch Removal and Reinstallation 34

DB-NE-06303 Fuel Handling in the Auxiliary Building 20

DB-NE-06307 Fuel Storage Handling Bridge Operating Procedure 12

DB-NE-06308 Main Fuel Handling Bridge Operating Procedure 14

DB-OP-02547 Spent Fuel Pool Cooling Malfunctions 08

DB-OP-06021 Spent Fuel Pool Operating Procedure 38

GEN-MNT- 0004 Foreign Material Exclusion 00

Inspection Type Designation Description or Title Revision or

Procedure Date

NG-DB-0017 Shutdown Defense in Depth Assessment 19

NOBP-OP-1004- Cycle 21 End of Cycle Shutdown While Restoring Tave to 02/24/2020

582F

Radiation CR-2020-02258 CF-4A1A Found Leaking (CF-LT3A1) 03/15/2020

Surveys

71111.22 Corrective Action CR 2020-01837 DB-SS-03708 Spent Fuel Pool Ventilation System Refueling 03/05/2020

Documents Interval Test Acceptance Criteria 5.3 Not Met

CR-2020-02423 Field Copy of DB-SC-03121 Lost Before Transferring Data to 03/19/2020

Master

Drawings E-1043 Sh 1 Emergency Diesel Generator 1-2 Loading Table 28

E-1043 Sh 2 Emer. Diesel Generator 1-2 Loading Table 30

Miscellaneous Recommended Enhanced Monitoring of the AFPT 2 02/14/2020

Governor and Governor Valve Linkage Prior/During the

Performance of DB-SP-03160 AFP 2 Quarterly Testing

Technical Requirements Manual 21

Procedures DB-SC-03022 Off-Site AC Sources Bus Transfer Test 20

DB-SC-03071 Emergency Diesel Generator 2 Monthly Test 37

DB-SP-03160 AFP 2 Quarterly Test 34

Work Orders 200756129 SFAS Train 2 Integrated Response Time Test 03/19/2020

200756227 SS3708-001 SFP Ventilation Test 03/05/2020

200817786 SFAS Component Test CV5075 03/17/2020

71124.01 Calculations DB-HP4344-01 Source Term Determination 08/02/2019

Calibration Containment Access Facility Exit Radiological Monitor Various

Records Calibration and Setpoint Data

Corrective Action CR-2019-05009 Elevated Contamination Levels Found in Clean Areas of 06/07/2019

Documents Auxiliary Building

CR-2019-08502 Continuous Noble Gas Monitor, AMS-4, Failed Due to Water 10/16/2019

Intrusion

CR-2019-08763 Individual Received a Dose Rate Alarm 10/22/2019

CR-2019-10082 Individual Alarmed Passive Monitoring 12/02/2019

CR-2019-10166 Elevated Dose Rates Identified in Dry Shielded Container 12/05/2019

Drain Port Hole

Procedures NOP-OP-4101 Access Controls for Radiologically Controlled Areas 16

Inspection Type Designation Description or Title Revision or

Procedure Date

NOP-OP-4102 Radiological Posting and Labeling 15

NOP-OP-4104 Job Coverage 11

NOP-OP-4701 Radiation and Contamination Surveys 3

Radiation Steam Generator Lower Bowl and Platform Radiological Various

Surveys Surveys and Air Sample Data

Radiation Work 120-5302 Once-Through Steam Generator Activities 0

Permits (RWPs)

71124.02 ALARA Plans 1R21 Refuel Outage Dose Estimate Trend 03/06/2020

Miscellaneous Shutdown Chemistry and Source Term Reduction Plan 1R21 0

RWP 120-5019 Alara Plan Waiver Form 11/16/2019

RWP 120-5405 Alara Work in Progress Review 03/04/2020

Procedures NOP-OP-4107 Radiation Work Permit (RWP) 18

Radiation Work 120-5104 Reactor Head Disassembly and Reassembly Work Activities 0

Permits (RWPs) 120-5304 Rotate Orifice Plate Inside Steam Generator 1-1 and 1-2 0

71151 Corrective Action CR 2019-00201 Steam Leak on MS100-1 Piping 01/08/2019

Documents

Miscellaneous Licensee Logs Various

NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7

71152 Corrective Action CR-2019-06415 CREATCS Train 2 Compressor Replacement Under Order 07/30/2019

Documents 200582815 was Not Identified as Yellow Nuclear Safety and

Generation Risk

CR-2019-06418 Critical Order ECP15-0138-004 Target Rock Work Order 07/30/2019

Dropped at T+1

CR-2019-06544 Chemistry Step in the WIS was Incorrectly Scheduled for the 08/04/2019

Auxiliary Boiler Outage

CR-2019-07192 On-line Preparation Milestones not Followed IAW NOP-WM- 08/28/2019

0001 Work Management Process

CR-2019-07763 System Leakage Test of CCW Pump #3 as #1 - Schedule 09/20/2019

Change at T-0

CR-2019-07864 Field Problem Resolution was not Processed Correctly 09/25/2019

CR-2019-09876 Unexpected Loss of Power on Security MUX6 Primary 11/22/2019

Communication AdTran

CR-2019-09925 AD110 HFA Relay Testing concerns 11/25/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-2019-09949 Poor Planning for #2 Circ Pump Maintenance 11/26/2019

CR-2019-10670 AFW Train 1 Lube PM Removed from Schedule at T5 and 12/30/2019

Placed Back into Schedule at NWW Without Crew

Acknowledgement

CR-2019-10674 LPI 1 Post-Quarterly Run Oil Sample Requires a Clearance 12/30/2019

and Determination to Defer the Sample not Completed at T2

CR-2020-00037 Switchyard Breaker 34560 Project Schedule Impacts 01/02/2020

CR-2020-01036 1R21 Orders Changing from RDEX to APLN for Additional 02/11/2020

Information

21