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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)
	v • d • e

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. 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

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.

REACTOR SAFETY

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)

Main article: IP 71111.08

(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)

Main article: IP 71111.22

(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)===

Main article: IP 71151