IR 05000382/2020004

Integrated Inspection Report 05000382/2020004

ML21034A420
Person / Time
Site:	Waterford
Issue date:	02/03/2021
From:	John Dixon NRC/RGN-IV/DRP
To:	Ferrick J Entergy Operations
References
IR 2020004
Download: ML21034A420 (22)

Text

February 3, 2021

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - INTEGRATED INSPECTION REPORT 05000382/2020004

Dear Mr. Ferrick:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Waterford Steam Electric Station, Unit 3. On January 14, 2021, 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, John L. Digitally signed by John L. Dixon Dixon Date: 2021.02.03 11:26:44 -06'00'

John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects Docket No. 05000382 License No. NPF-38

Enclosure:

As stated

Inspection Report

Docket Number: 05000382 License Number: NPF-38 Report Number: 05000382/2020004 Enterprise Identifier: I-2020-004-0002 Licensee: Entergy Operations, Inc.

Facility: Waterford Steam Electric Station, Unit 3 Location: Killona, LA 70057 Inspection Dates: October 1, 2020 to December 31, 2020 Inspectors: R. Alexander, Senior Emergency Preparedness Inspector D. Antonangeli, Health Physicist D. Childs, Resident Inspector J. Drake, Senior Reactor Inspector L. Flores, Reactor Inspector N. Greene, Senior Health Physicist R. Kopriva, Senior Reactor Inspector A. Patz, Senior Resident Inspector F. Ramirez Munoz, Senior Reactor Inspector Approved By: John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Waterford Steam Electric Station, Unit 3, 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

Waterford, Unit 3, began the inspection period in a refueling outage. On October 31, 2020, Unit 3 was restarted and inadvertently tripped on November 2, 2020, due to an issue with the control element drive mechanism control system. Unit 3 was restarted on November 4, 2020, and achieved full power on November 15, 2020. On November 27, 2020, the licensee performed an emergent downpower to approximately 90 percent power to address governor valve oscillations and returned to full power on December 1, 2020. On December 11, 2020, the licensee initiated a rapid downpower into hot standby due to a steam leak near the turbine governor valves. On December 14, 2020, Unit 3 was restarted and remained at full power until the end 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.

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 Disease 2019 (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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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 some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

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

(1) Emergency diesel generator A with emergency diesel generator B out of service for maintenance, on October 19, 2020

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the shutdown cooling system, on October 20, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

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) Fire Area RCB-001, reactor containment building general area, on October 15, 2020

(2) Fire Area RAB 13-001, battery rooms, on October 30, 2020

(3) Fire Area ROOF E-001, main steam isolation valve B, on November 3, 2020

(4) Fire Area ROOF W-001, main steam isolation valve A, on November 3, 2020

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

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from October 8, to November 20, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

• Eddy Current Examination, RCP 1A Motor Flywheel (Entire Flywheel), Report Number: ISI-ET-20-001

• Dye Penetrant Examination, RAB-Safeguards Pump Room B Containment Spray Anchor Attachment Weld, Report Number: ISI-PT-20-001

• Magnetic Particle Examination, Wet MSIV Area Main Steam Welded Support to 40-inch Pipe, Report Number: ISI-MT-20-004

• Visual Examination VT-3, RCB+46 West D-Ring Safety Injection Bolted Connection SG MSG001, Report Number: ISI-VT-20-048

• Visual Examination VT-3, Cooling Tower Area A Component Cooling Water Rigid Restraint, Report Number: ISI-VT-20-113

• Visual Examination VT-1, Cooling Tower Area A Component Cooling Water Rigid Restraint, Report Number: ISI-VT-30-114

• Visual Examination VT-3, West MSIC Area Main Steam Rigid Restraint, Report Number: ISI-VT-20-096

• Ultrasonic Examination, RCB-Loop 2 D-Ring S/G #2 Main Steam Tube sheet to Lower Shell Weld, Report Number: ISI-UT-20-005

• Ultrasonic Examination, RAB-East Wing Area Safety Injection Elbow to 8-inch Pipe Weld, Report Number: ISI-UT-20-004

• Ultrasonic Examination, Loop 1A Safety Injection 12-inch Pipe to 45 Degree Elbow Weld, Report Number: ISI-UT-20-006

• Ultrasonic Examination, Loop 1A Safety Injection 45 Degree Elbow to 12-inch Pipe Weld, Report Number: ISI-UT-20-007

• Ultrasonic Examination, Loop 1A Safety Injection 12-inch Pipe to 45 Degree Elbow Weld, Report Number: ISI-UT-20-008

• Ultrasonic Examination, RCP 1A Motor Flywheel (Entire Flywheel), Report Number: ISI-UT-20-013

• Welding: Work Order 520048-005, Weld Map No. 520048-05-01, Reference Drawing No. E3029LW3RC25, Flange to Pipe Weld SW 12 (Fillet Weld)

• Welding: Work Order 520048-97, Weld Map No. 520048-07-01, Reference Drawing No. E3029LW3RC25 -- A193-134, Support - Field Welds FW1 and FW2 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

• Waterford 3 started Refueling Outage RF23 in October 2020. Waterford 3 installed a new reactor head with A690 welds during Refueling Outage RF 18, spring of 2013. 10CFR50.55a requires implementation of Code Case N-729-6. Inspection of replacement head is: Bare Metal Visual for Item No. B4.30 every 3rd Refuel or 5 years. The next scheduled reactor head inspection utilizing Code Case N-729-6 is during Refueling Outage RF24.

Between Refueling outage RF20 and RF21, the licensee experienced a component cooling water leak on the reactor head cooling water system, which ended up depositing molybdates on the reactor head. The reactor head was cleaned, but some residual material remained. During Refueling Outage RF22 more cleaning of the reactor head was performed. In August of 2020, the licensee experienced a leak in two incore instrumentation tubes, which sprayed boric acid over a large area, above the reactor head, in the insulation package. The licensee cleaned up most of the boric acid residue but did not perform any cleaning on the boric acid that had run across the insulation package and down the control rod drive mechanism housings and onto the reactor head. During the current Refueling Outage RF23, the licensee identified all the areas on the reactor head that had boric acid residue. The licensee took samples and ran chemical analyses on them to confirm that the radionuclides found in the samples were from the August time frame and not recent leakage of boric acid. The licensee also used the inspection crawler (utilized during required Code Case N-729-6 visual examination) to inspect all the reactor head penetrations.

Upon completion of the reactor head examination, and when the licensee confirmed that there were no active leaks from any reactor head penetration, the reactor head was cleaned using dry ice particles.

03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

• Boric Acid Evaluation: 19-WF3-0003, Condition Report CR-WF3-18-6844

• Boric Acid Evaluation: 19-WF3-0004, Condition Report CR-WF3-19-0140

• Boric Acid Evaluation: 19-WF3-0012, Condition Report CR-WF3-19-1063

• Boric Acid Evaluation: 19-WF3-0017, Condition Report CR-WF3-19-2089

• Boric Acid Evaluation: 19-WF3-0021, Condition Report CR-WF3-19-3302

• Boric Acid Evaluation: 19-WF3-0023, Condition Report CR-WF3-19-4894

• Boric Acid Evaluation: 19-WF3-0025, Condition Report CR-WF3-19-6358

• Boric Acid Evaluation: 19-WF3-0026, Condition Report CR-WF3-19-6379

• Boric Acid Evaluation: 19-WF3-0028, Condition Report CR-WF3-19-5755

• Boric Acid Evaluation: 19-WF3-0034, Condition Report CR-WF3-19-6603

• Boric Acid Evaluation: 20-WF3-0001, Condition Report CR-WF3-20-1131

• Boric Acid Evaluation: 20-WF3-0004, Condition Report CR-WF3-20-3933

• Boric Acid Evaluation: 20-WF3-0013, Condition Report CR-WF3-20-4592 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities

• No Steam Generator inspections were required or scheduled during Refueling Outage RF23.

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 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during drain down activities to lower reactor coolant system inventory for reinstallation of the reactor vessel head on October 21, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a simulator scenario during a licensed operator examination on November 16, 2020.

71111.12 - Maintenance Effectiveness

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) Essential chilled water system, on December 18, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

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) Emergent orange shutdown risk due to the failure of startup channel 2, on October 6, 2020

(2) Emergent failure of high-pressure safety injection pump B during surveillance testing, on October 14, 2020

(3) Emergent work on feedwater heater 2C level control valve following its failure and impact on reactor power, on November 12, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:

(1) Operability determination of reactor coolant loop 2 shutdown cooling upstream suction isolation valve following identification of a magnesium rotor in the motor, on November 16, 2020

(2) Operability determination of high-pressure safety injection train A due to pump low recirculation flow, on November 17, 2020

(3) Operability determination of the control room emergency filtration system following failure of two dampers for the B unit, on December 15, 2020

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)

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

(1) Emergency diesel generator B following planned maintenance, on October 19, 2020

(2) Feedwater isolation valve A following planned maintenance, on October 22, 2020

(3) Atmospheric dump valve B following planned maintenance, on October 22, 2020

(4) Reactor coolant loop 1 shutdown cooling upstream suction isolation valve following failure to stroke, on November 4, 2020

(5) Chemical volume and control pump AB following planned maintenance, on November 25, 2020

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage 23 activities from September 25, to November 1, 2020, which completes the partial sample documented in Waterford Inspection Report 05000382/2020003, Section 71111.20.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Containment sump trisodium phosphate storage basket inspection, on November 17, 2020

(2) Turbine trip testing, on December 14, 2020

(3) Control room emergency filtration unit B testing, on December 16, 2020

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Containment atmospheric release exhaust header A inlet and upstream isolation valves, on October 19, 2020

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the maintenance and testing of the alert and notification system between September 1, 2018 and November 30, 2020.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the Emergency Preparedness Organization between September 1, 2018 and November 30, 2020.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated the 10 CFR 50.54(q) emergency plan change process and practices between September 1, 2018 and November 30, 2020. This involved review of licensee screening and evaluation documentation. The reviews of the change process documentation do not constitute NRC approval.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program between September 1, 2018 and November 30, 2020.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) Emergency preparedness training evolution in the control room simulator, on November 18,

OTHER ACTIVITIES - BASELINE

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

EP01: Drill/Exercise Performance (IP Section 02.12) ===

(1) October 1, 2019, through September 30, 2020

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) October 1, 2019, through September 30, 2020

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) October 1, 2019, through September 30, 2020 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) October 1, 2019, through September 30, 2020

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) October 1, 2019, through September 30, 2020

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) January 1, 2019, through September 30, 2020 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) January 1, 2019, through September 30, 2020

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

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

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

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

(1) High pressure safety injection pump B breaker issues, on October 27, 2020

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

(1) The inspectors evaluated the licensees response to an automatic reactor trip due to control element drive mechanism control system timer failure on November 2,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On December 11, 2020, the inspectors presented the emergency preparedness program inspection results to Mr. J. Ferrick, Site Vice President, and other members of the licensee staff.

• On January 7, 2021, the inspectors presented the inservice inspection results to Mr. M. Lewis, General Manager of Plant Operations, and other members of the licensee staff.

• On January 14, 2021, the inspectors presented the integrated inspection results to Mr. J. Ferrick, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Date

Procedure

71111.04 Procedures OP-009-002 Emergency Diesel Generator 354

OP-009-005 Shutdown Cooling 044

71111.05 Corrective Action CR-WF3-YYYY- 2020-06250

Documents NNNN

Miscellaneous RAB 13-001 Waterford S.E.S Prefire Strategy Battery Room AB 007

RCB-001 Waterford S.E.S Prefire Strategy RCB General Area 011

ROOF E-001 Waterford S.E.S Prefire Strategy Elevation +46 Roof E 005

MSIV B

ROOF W-001 Waterford S.E.S Prefire Strategy Elevation +46 ROOF W 002

MSIV A

71111.08P Corrective Action CR-WF3-YYYY- 2019-0617, 2019-0762, 2020-1078, 2019-4461,

Documents NNNN 2019-4223, 2019-1758, 2019-5652, 2019-8604,

20-0180, 2020-0375, 2019-3685, 2020-2987,

2019-0931, 2019-6456, 2020-3718, 2019-0416,

20-3327, 2019-00719, 2019-03679, 2019-03685,

2019-04683, 2019-04694, 2020-04843, 2020-04845,

CR-HQN-2019, CR-HQN-2019-1125,

CR-HQN-2019-2482, CR-HQN-2019-0957,

CR-HQN-2019-2716, CR-HQN-2019-1060

Drawings 5817-10936 ICI Adapter Assembly 0

5817-11178 Type "B" HJTC Cable Assembly (RDP to RAS) 0

5817-11772 ICI & HJTC Quickloc Assembly, Sheet 1 2

E-9270-164-005 Nozzle Requirements Closure Head 9

LDRAC No. Closure Head Assembly 0

5817-13747,

Sheet 1

Engineering EC# 0000081552 Disposition of Active Leak Found on Reactor 0

Changes

Engineering Evaluation #: 19- Boric Acid Walkdown, Reactor Head, ICI #5 08/02/2019

Evaluations WF3-0025

Evaluation #: 19- Boric Acid Walkdown, Reactor Head, ICI #8 08/03/2019

WF3-0026

Inspection Type Designation Description or Title Revision or Date

Procedure

Miscellaneous 17-WF3-0128 Boric Acid Leakage Identification. Component ID#: 12/28/2017

PSLMVAAA204, Location: RAB

EPID L-2018- Waterford Steam Electric Station, Unit 3-Authorization of 06/12/2019

LLR-0125 Proposed Alternative to ASME Code Case N-770-2 (EPID

L-2018-LLR-0125)

EPID L-2019- Waterford Steam Electric Station, Unit 3 - Authorization of 08/27/2019

LLR-0003 Proposed Alternative to ASME Code,Section XI, IWA-

4000, "Repair/Replacement Activities."

PQR-024 Procedure Qualification Record, Manual Gas tungsten & 1

Shielded Metal Arc Welding (GTAW & SMAW), Base

Metal: P-No.1, SA-106 Gr. B

PQR-107 Procedure Qualification Record, Manual Gas Tungsten & 1

Shielded Metal Arc Welding (GTAW & SMAW), Base

Metal: P-No.8, SA-312 Type 304

PQR-170 Manual Gas Tungsten & Shielded Metal Arc Welding 1

(GTAW & SMAW), Base Metal: P-No.8, SA-240 Type 304

PQR-330 Manual Gas Tungsten & Shielded Metal Arc Welding 1

(GTAW & SMAW), Base Metal: P-No.1, Group 1 to 2,

SA-516 Gr. 60 to SA-516 Gr. 60 to SA-516 Gr. 70

PQR-331 Manual Gas Tungsten & Shielded Metal Arc Welding 1

(GTAW & SMAW), Base Metal: P-N0.1, Group 1 to 2,

SA-516 Gr. 60 to SA-516 Gr. 70

W3F1-2008-0060 Request for Alternative W3-iSI-006, Proposed Alternative 09/18/2008

to Extend the Second 10-Year Inservice, Inspection

Interval for Reactor Vessel Internal Weld Examinations,

Waterford Steam Electric Station, Unit 3, Docket No.

50-382, License No. NPF-38

W3F1-2009-0006 RAI Response to Request for Alternative W3-ISI-006 To 03/19/2009

Extend the Second, 10 Year AMSE Code ISI and License

Amendment Request, NPF-38-280 To Support Request

for Alternative W3-ISI-006, Waterford Steam Electric

Station, Unit 3 (Waterford 3), Docket No. 50-382, License

No. NPF-38

W3F1-2013-0044 Waterford 3 Request for Alternative W3-ISI-023, ASME 09/26/2013

Inspection Type Designation Description or Title Revision or Date

Procedure

Code Case N-770-1, Successive Examinations, Waterford

Steam Electric Station, Unit 3, Docket No. 50-382,

License No. NPF-38

W3F1-2013-0044 Waterford 3 Request for Alternative W3-ISI-023, ASME 09/26/2013

Code Case N-770-1, Successive Examinations, Waterford

Steam Electric Station, Unit 3, Docket No. 50-382

License No. NPF-38

W3F1-2018-0008 Request for NRC Alternative to ASME IWA-5211 02/20/2018

Regarding Charging Pipe, Visual Inspection, Relief

Request W3-ISI-030, Waterford Steam Electric Station,

Unit 3 (Waterford 3)

Docket No. 50-382, License No. NPF-38

W3F1-2018-0067 Response to NRC Request for Additional Information 11/19/2018

Regarding Request for, Alternative to ASME Code Case

N-770-2, Successive Examinations, Relief, Request

W3-ISI-031

W3F1-2019-0009 Proposed Inservice Inspection Program Alternative 01/28/2019

WF3-RR-19-1 for Application of Dissimilar Metal Weld Full

Structural Weld Overlay - Reactor Coolant System Cold

Leg Drain Nozzles

W3F1-2019-0017 Closure of Commitment Associated with Inservice 02/14/2019

Inspection Program, Alternative WF3-RR-19-1 for

Application of Dissimilar Metal Weld Full, Structural Weld

Overlay - Reactor Coolant System Cold Leg Drain

Nozzles

W3F1-2019-0049 Commitment Change Notification and Closure of 07/16/2019

Commitment Associated with Inservice Inspection

Program Alternative WF3-RR-19-1 for Application of

Dissimilar Metal Weld Full Structural Weld Overlay -

Reactor Coolant System Cold Leg Drain Nozzles

W3F1-2020-0055 10 CFR Part 21 Report: Defect of Masoneilan 8012N-3C 09/01/2020

Electropneumatic Positioner. Waterford Steam Electric

Station, Unit 3 (Waterford 3), NRC Docket No. 50-382

Renewed Facility Operating License No. NPF-38

Inspection Type Designation Description or Title Revision or Date

Procedure

WPS-CS-1/1-C Shielded Metal Arc Welding (SMAW) of P-No,1 carbon 0

steels, in all positions, for all joint types, fillets and repairs

using A-No.1 carbon steel filler metal, with or without

Postweld Heat Treatment (PWHT).

WPS-SS-8/8-B Manual Gas Tungsten Arc Welding (GTAW) of P-No.8 0

stainless steels, in all positions, for all joint types, fillets

and repairs using A-N0.8 stainless steel filler metal,

without Postweld Heat Treatment (PWHT).

NDE Reports BOP-VE-19-002 RCS Loop 1A Lower Cold Leg, Nozzle to Safe End 02/06/2019

Circumferential Weld, Component ID: 07-009-WOL

BOP-VT-19-005 Reactor Cavity, RVCH CEDM Nozzles. 02/01/2019

ISI-VE-19-009 RCS Loop 1A Lower Cold Leg, Nozzle to Safe-End 01/16/2019

Circumferential Weld. Component ID: 07-009

ISI-VE-19-013 RCS Loop 2A Lower Cold Leg, Nozzle to Safe-End 01/24/2019

Circumferential Weld. Component ID: 00-007

ISI-VT-19-038 Cooling Tower Area B, Rigid Restraint. Component ID: 01/14/2019

CCRR-0393

ISI-VT-19-063 Loop 2A, Rigid Restraint, Component ID: RCRR-0094 01/19/2019

ISI-VT-19-064 Loop 2A, Rigid Restraint. Component ID: RCRR-0182 01/19/2019

ISI-VT-20-008 RAB - 4 Wing Area, Sampling - RAB, Component ID: 02/12/2020

13.3.3

ISI-VT-20-029 RAV-MSIV Area, N2 Accumulator VI Subsystem, 05/26/2020

Component ID: 13.3.26

Procedures CEP-BAC-001 Boric Acid Corrosion Control (BACC) Program Plan, 2

Entergy Nuclear Engineering Programs.

CEP-ISI-100 ASME Section XI, Division 1, Fleet Administrative 5

Controls for Inservice Inspection Program, Entergy

Nuclear Engineering Programs

CEP-NDE-0400 Ultrasonic Examination, Entergy Nuclear Engineering 8

Programs

CEP-NDE-0404 Manual Ultrasonic Examination of Ferritic Piping Welds 9

(ASME XI), Entergy Nuclear Engineering Programs

CEP-NDE-0423 Manual Ultrasonic Examination of Austenitic Piping Welds 9

(ASME XI), Entergy Nuclear Engineering Programs

Inspection Type Designation Description or Title Revision or Date

Procedure

CEP-NDE-0493 Manual Ultrasonic Examination of Reactor Coolant Pump 4

Flywheel, Entergy Nuclear Engineering Programs

CEP-NDE-0497 Manual Ultrasonic Examination of Weids in Vessels (Non- 7

App. VIII), Entergy Nuclear Engineering Programs

CEP-NDE-0497 Manual Ultrasonic Examination of Welds in Vessels (Non- 7

App. VIII), Entergy Nuclear Engineering Programs

CEP-NDE-0730 Non-Section XI Magnetic Particle Examination (MT), 7

Entergy Nuclear Engineering Programs

CEP-NDE-0731 Magnetic Particle Examination (MT) for ASME Section XI, 6

Entergy Nuclear Engineering Programs

CEP-NDE-0901 VT-1 Examination, Entergy Nuclear Engineering 6

Programs

CEP-NDE-0903 VT-3 Examination, Entergy Nuclear Engineering 6

Programs

EIP-PT-001 ASME Section XI Pressure Test (PT) Program, Entergy 310

Nuclear Engineering Programs.

EN-DC-319 Boric Acid Corrosion Control Program (BACCP) 12

EN-DC-328 Entergy Nuclear Welding Program 6

RF-001-013 Incore Instrument Flanges 315

SEP-BAC-WF3- Waterford 3 Boric Acid Corrosion Control Program 2

001 (BACCP) Program Section SEP-BAC-WF3-001

SEP-CISI-104 Program Section for ASME Section XI, Division 1, WF3 4

Containment Inservice Inspection Program, Entergy

Nuclear Engineering Programs

SEP-ISI-104 Program Section for ASME Section XI, Division 1, WF3 9

Inservice Inspection program, Entergy Nuclear

Engineering Programs

SEP-ISI-104 Program Section for ASME Section XI Division 1 WF3 9

Inservice Inspection Program, Entergy Nuclear

Engineering Programs

Self- LO-WLO-2019- Pre-NRC RF23 ISI Activities Self-Assessment Report 06/29/2020

Assessments 00031

Work Orders Work Orders 527322-01

71111.12 Corrective Action CR-WF3-YYYY- 2019-08796, 2019-08801, 2019-08806, 2019-08826,

Inspection Type Designation Description or Title Revision or Date

Procedure

Documents NNNN 2019-08839, 2020-03991, 2020-05725, 2020-06388

71111.13 Corrective Action CR-WF3-YYYY- 2020-05855

Documents NNNN

Procedures EN-WM-104 On-Line Risk Assessment 022

OI-037-000 Operations Risk Assessment Guideline 315

71111.15 Miscellaneous W3-DBD-038 Safety-Related HVAC - Control Room Design Basis 301

Document

71111.19 Corrective Action CR-WF3-YYYY- 2020-05885

Documents NNNN

71111.22 Corrective Action CR-WF3-YYYY- 2020-07126 12/17/2020

Documents NNNN

Miscellaneous Process Applicability Determination Form For OP-903- 09/22/2020

115, Revision 052

FSAR Section AC Power Systems

8.3.1

Technical A.C. Sources

Specification

3/4.8.1

Procedures ME-007-002 Molded Case Circuit Breakers 28

OP-903-027 Inspection of Containment 306

OP-903-115 Train A Integrated Emergency Diesel

Generator/Engineering Safety Features Test

OP-903-123 Control Room Envelope Pressure Test 311

STA-001-004 Surveillance Procedure Local Rate Test 318

Work Orders 157704 Perform Maintenance on Breaker Referencing 09/03/2013

ME-007-002

71114.02 Corrective Action CR-WF3-YYYY- 2018-05551, 2018-05591, 2018-07075, 2019-04362,

Documents NNNN 2019-06326, 2019-06327, 2019-08824, 2019-08930,

20-03581, 2020-04021, 2020-04022, 2020-04023,

20-04507, 2020-06251

Miscellaneous Updated Alert/Notification System Design Report 8 (Addendum 0,

(December 2014) Revision 1)

KLD TR-825 Waterford 3 Steam Electric Station: 2015 - Population by 02/19/2016

Siren Contour Analysis Update

Inspection Type Designation Description or Title Revision or Date

Procedure

Procedures EPP-422 Siren and Helicopter Warning System Maintenance 013

EPP-424 Siren Testing and Siren System Administrative Controls 020

71114.03 Corrective Action CR-WF3-YYYY- 2018-05402, 2018-07228, 2019-04576, 2019-06270,

Documents NNNN 2019-07314, 2019-07397, 2019-07817, 2020-01181,

20-02280, 2020-02886

Miscellaneous ERO Callout Test Analysis Results (Multiple Quarterly 3Q/2018 -

and Monthly Reports) 3Q/2020

Waterford 3 Station On-Shift Staffing Analysis Final 1

Report (April 4, 2017)

Procedures EN-EP-310 Emergency Response Organization Notification System 009

EP-002-015 Emergency Responder Activation 304

EPP-462 Evaluation of ERO Callout Test 5

71114.04 Corrective Action CR-WF3-YYYY- 2019-08175, 2019-08488, 2020-00857

Documents NNNN

Miscellaneous 10 CFR 50.54(Q)(3) Screening & Evaluation: EP-002-010, 04/24/2019

Rev 316

CFR 50.54(Q)(3) Screening & Evaluation: EN-EP-313, 10/25/2019

Rev. 003

CFR 50.54(Q)(2) Review: Plant Entrance and Exit 03/24/2020

Points (for COVID-19 Screening)

CFR 50.54(Q)(2) Review: EN-EP-609, EOF 02/17/2020

Operations, Rev 6

CFR 50.54(Q)(2) Review: EP-001-010, Unusual Event, 02/04/2019

Rev 307

CFR 50.54(Q)(2) Review: EP-001-020, Alert, Rev 310 02/04/2019

CFR 50.54(Q)(2) Review: EP-001-030, Site Area 02/08/2019

Emergency, Rev 309

CFR 50.54(Q)(2) Review: EP-001-040, General 02/08/2019

Emergency, Rev 310

CFR 50.54(Q)(2) Review: EP-002-052, Protective 04/24/2019

Action Guidelines, Rev 026

Procedures EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 7&8

71114.05 Corrective Action CR-WF3-YYYY- 2018-06295, 2018-07047, 2019-00361, 2019-00399,

Documents NNNN 2019-00401, 2019-03651, 2019-04353, 2019-06431,

Inspection Type Designation Description or Title Revision or Date

Procedure

2019-06444, 2019-07149, 2019-07467, 2019-07477,

2019-07547, 2019-07722, 2019-08611, 2019-08638,

2019-08640, 2019-08711, 2020-00228, 2020-01114,

20-01180, 2020-01319, 2020-01325, 2020-01992,

20-06193

Corrective Action CR-WF3-2020-07046, WTWF3-2020-00381

Documents

Resulting from

Inspection

Miscellaneous ERO Red Team Drill (3/4/2020) Report 04/03/2020

ERP Blue Team Drill (4/3/2019) Report 04/15/2019

ERO Red Team Site Drill (4/30/2019) Report 05/30/2019

TSC Limited Scope Focused Drill 2019-07 Report 05/13/2019

ERO Orange Team NRC Dress Rehearsal Drill 10/23/2019

(9/25/2019) Report

TSC Operations Coordinator Focused Drill 2019-05 03/11/2019

ERO Blue Team Site Drill (12/6/2018) Report 01/20/2019

HP Drill Report (12/09/2019) 12/17/2019

HP Drill Report (06/20/2019 - #2019-08) 10/01/2019

Onsite Medical Drill Report (10/30/2019) 12/03/2019

ERO Orange Team NRC Exercise (11/20/2019) Report 12/17/2019

Waterford Emergency Plan - Appendix C (Letters of Various(Updated

Agreement with Hahnville Volunteer Fire Department, 2019-2020)

U.S. Coast Guard, St. Charles Parish Sheriffs Office, &

Panther Helicopter)

Waterford Emergency Plan - Appendix I (Emergency Various

Medical Assistance Program, Letters of Agreement with (Updated 2019 -

St. Charles Parish Hospital and West Jefferson Medical 2020)

Center)

Waterford 3 Steam Electric Station Emergency Plan 50, 51

Emergency Focused Drill for Site Accountability 12/28/2018 &

Preparedness 11/27/2019

Focused

Tabletop #2017-

Inspection Type Designation Description or Title Revision or Date

Procedure

KLD TR-1017 Waterford-3 Steam Electric Station 2018 Population 09/08/2018

Update Analysis

KLD TR-1092 Waterford-3 Steam Electric Station 2019 Population 09/07/2019

Update Analysis

KLD TR-1172 Waterford-3 Steam Electric Station 2020 Population 09/05/2020

Update Analysis

KLD TR-502 Waterford-3 Steam Electric Station Development of 11/2012

Evacuation Time Estimates

QA-7-2019-W3-1 Audit Report: Emergency Preparedness (10 CFR 50.54(t) 05/13/2019

Program Review)

QA-7-2020-W3-1 Audit Report: Emergency Preparedness (10 CFR 50.54(t) 05/18/2020

Program Review)

Trimester 19-02 Nuclear Independent Oversight Functional Area 10/20/2019

Performance Report

Trimester 20-01 Nuclear Independent Oversight Functional Area 03/17/2020

Performance Report

Trimester 20-02 Nuclear Independent Oversight Functional Area 06/29/2020

Performance Report

Trimester 20-03 Nuclear Independent Oversight Functional Area 10/23/2020

Performance Report

W3D3-2019-0001 Summary Drill Report: Control Room Emergency 05/08/2019

Breathing Air Drill (Scenario #2019-06)

W3D3-2019-0002 Summary Drill Report: Control Room Emergency 12/06/2019

Breathing Air Drill (Scenario #2019-06)

W3D3-2020-01 Summary Drill Report: Control Room Emergency 04/30/2020

Breathing Air Drill (Scenario #2020-08)

W3D3-2020-02 Summary Drill Report Control Room Emergency 08/24/2020

Breathing Air Drill (Scenario #2020-10)

Procedures EN-LI-102 Corrective Action Program 41

EP-001-001 Recognition and Classification of Emergency Conditions 33

EP-002-052 Protective Action Guidelines 026

EP-002-071 Site Protective Measures 304

EP-003-040 Emergency Equipment Inventory 310

Inspection Type Designation Description or Title Revision or Date

Procedure

EPP-428 Equipment Important to Emergency Response 307

Self- LO-WLO-2019- Pre-NRC Evaluated Exercise Assessment 09/09/2019

Assessments 00024

LO-WLO-2020- 2020 Pre-NRC Emergency Planning Program Inspection 08/24/2020

00041 Assessment

Work Orders WO-WF3-NNNN 00333437, 00489973, 00495967, 00511576,

0052930321, 0052930321, 0052933267

71151 Corrective Action CR-WF3-YYYY- 2020-07050

Documents NNNN

Resulting from

Inspection

Miscellaneous WF3 Key ERO Member Participation Reports & ERO 4Q/2019-

Rosters 3Q/2020

WF3 Drill and Exercise Performance Indicator Records 4Q/2019 -

(from License Operator Exam/Requalification, Team 3Q/2020

Drills, and other ERO Activities)

WF3 ANS (Fixed Siren) Testing Records 4Q/2019 -

3Q/2020

Procedures EN-EP-801 Emergency Response Organization 17

EN-FAP-EP-005 Emergency Preparedness Performance Indicators 14

EN-LI-117 Regulatory Performance Indicator Process 17

71152 Corrective Action CR-WF3-YYYY- 2020-03400

Documents NNNN

Resulting from

Inspection

Procedures MM-007-010 Fire Extinguisher Inspection and Extinguisher 325

Replacement

20