IR 05000382/2022004

Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001

ML23025A100
Person / Time
Site:	Waterford
Issue date:	01/26/2023
From:	Alfred Sanchez NRC/RGN-IV/DORS/PBD
To:	Ferrick J Entergy Operations
References
IR 2022001
Download: ML23025A100 (22)

Text

January 26, 2023

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - INTEGRATED INSPECTION REPORT 05000382/2022004 AND INDEPENDENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200075/2022001

Dear John Ferrick:

On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Waterford Steam Electric Station, Unit 3. On January 17, 2023, 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 NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Waterford Steam Electric Station, Unit 3. 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, Signed by Dixon, John on 01/26/23 John L. Dixon, Jr, Chief Projects Branch D Division of Operating Reactor Safety Docket Nos. 05000382, 07200075 License No. NPF-38

Enclosure:

As stated

Inspection Report

Docket Number: 05000382 and 07200075 License Number: NPF-38 Report Number: 05000382/2022004 and 07200075/2022001 Enterprise Identifier: I-2022-004-0007 and 1-2022-001-0107 Licensee: Entergy Operations, Inc.

Facility: Waterford Steam Electric Station, Unit 3 Location: Killona, Louisiana 70057 Inspection Dates: October 1, 2022, to December 31, 2022 Inspectors: L. Brookhart, Senior Spent Fuel Storage Inspector D. Childs, Resident Inspector S. Hedger, Sr Emergency Preparedness Inspector R. Kumana, Senior Resident Inspector A. Patz, Senior Resident Inspector A. Sanchez, Senior Project Engineer H. Strittmatter, Emergency Preparedness Inspector Approved By: John L. Dixon, Jr, Chief Projects Branch D Division of Operating Reactor Safety 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. A licensee-identified non-cited violation is documented in the Inspection Results section of the report.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000382/2022-002-00 Operation Prohibited by 71153 Closed Technical Specifications Due to Personnel Error

PLANT STATUS

Unit 3 began the inspection period at rated thermal power and remained at or near rated thermal power for 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 activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather and tornadic conditions on December 14, 2022.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

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

(1) containment spray train A while train B was inoperable for surveillance testing on October 13, 2022

(2) startup transformer B and emergency diesel generators while startup transformer A was inoperable during planned maintenance on November 1, 2022

(3) high pressure safety injection train B while train A was inoperable during planned maintenance on November 9, 2022

(4) controlled ventilation area system train B while train A was inoperable during planned maintenance on November 17, 2022

(5) low pressure safety injection train B while train A was inoperable during planned maintenance on December 1, 2022

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

(1) The inspectors evaluated system configurations during a complete walkdown of train B of the component cooling water system on December 22, 2022.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 RAB 33-001, elevation -35.00' reactor auxiliary building shutdown cooling heat exchanger rooms on October 4, 2022

(2) fire area RAB 35-001, elevation -35.00' reactor auxiliary building safety injection pump room B on November 7, 2022

(3) fire area NS-TB-005, elevation +67.00' turbine building operating floor on December 13, 2022

(4) fire area RAB-39-001, elevation -35.00' reactor auxiliary building general area on December 30, 2022

(5) fire area ROOF E-001, elevation +46.00' reactor containment building east main steam isolation valve area on December 30, 2022

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill in the -4.00' elevation of the reactor auxiliary building involving a person trapped inside a room on October 14, 2022.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) reactor auxiliary building areas that are impacted by condensate storage pool and the reactor water storage pool flooding events on December 2, 2022

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(2 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the control room during a train swap for the swing AB bus on October 21, 2022.

(2) The inspectors observed and evaluated licensed operator performance in the control room during a containment entry for a core protection calculator modification on November 23, 2022.

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

(1) The inspectors observed and evaluated licensed operator simulator training involving a control room fire and evacuation on December 13, 2022.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

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

(1) essential services chilled water system on October 4, 2022

(2) controlled ventilation area system train B following failure of inlet damper on December 23, 2022

(3) containment spray system train B failure of engineered safety function actuation signal test due to supply breaker interlock switch failure on December 29, 2022

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) startup transformer B on December 12, 2022

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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) yellow risk due to unavailability of makeup water to the volume control tank and refueling water storage pool during planned flow rate monitor calibration on October 11, 2022

(2) elevated green risk due to a failure of the nitrogen gas isolation valve to train B emergency feedwater system and atmospheric dump valve actuators on October 20, 2022

(3) yellow risk due to unavailability of startup transformer A during planned maintenance on November 1, 2022

(4) elevated green risk due to the planned outage of controlled ventilation area system train B from November 15-18, 2022

(5) yellow risk due to the unavailability of low pressure safety injection train A during planned maintenance and unplanned maintenance to replace a breaker for valve SI-125A on December 1, 2022

(6) elevated green risk due to planned emergency diesel generator A outage and unplanned essential services chilled water chiller B outage from December 5-8, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) wide range gas monitor operability determination following discovery of incorrect alarm setpoints on October 26, 2022

(2) liquid effluent radiation monitoring operability determination following discovery of incorrect engineering conversion factors on November 16, 2022

(3) essential services chilled water train B operability determination following discovery of equipment issues for both chiller AB and chiller B on November 18, 2022

(4) auxiliary component cooling water train B operability determination following automatic start and manual securing of auxiliary component cooling water pump B on December 9, 2022

71111.18 - Plant Modifications

Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)

(1) The inspectors verified the site Severe Accident Management Guidelines were updated in accordance with the PWR generic severe accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, revision 1, on November 9, 2022.

71111.19 - Post-Maintenance Testing

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

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

(1) personnel containment hatch interlock test following preventive maintenance on October 5, 2022

(2) Testing of the nitrogen gas supply system to train B emergency feedwater system and atmospheric dump valve actuators following surveillance testing failure on October 24, 2022

(3) containment fan cooler D testing following power cable replacement on October 27, 2022

(4) low pressure safety injection pump A and valve SI-125 testing following planned maintenance and an unplanned breaker replacement on December 2, 2022

(5) essential services chilled water chiller B testing following corrective maintenance on December 10, 2022

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Inservice Testing (IP Section 03.01) (1 Sample)

(1) low pressure safety injection pump A on November 29, 2022

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) reactor coolant system leakage testing following identification of an increasing trend of unidentified leakage on November 25, 2022

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 November 31, 2020, and December 9, 2022.

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 November 31, 2020, and December 9, 2022. Inspectors also evaluated the licensee's ability to staff their emergency response facilities in accordance with emergency plan commitments.

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 November 31, 2020, and December 9, 2022. The evaluation reviewed screenings and evaluations documenting implementation of the process. In addition, the inspectors evaluated the following emergency plan revisions:

Recognition and Classification of Emergency Conditions, EAL Basis Document (EP-001-001), revision 37 (effective October 25, 2022)

Recognition and Classification of Emergency Conditions Wall Chart (EP-001-001-01 WC), revision 1 (effective October 25, 2022)

The reviews of the change process documentation or the emergency plan changes 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 November 31, 2020, and December 9, 2022. The evaluation reviewed evidence of completing various emergency plant commitments, the conduct of drills and exercises, licensee audits and assessments, and the maintenance of equipment important to emergency preparedness.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)

The inspectors evaluated:

(1) a licensed operator training evolution in the simulator including a loss of pressurizer level indication, a leaking waste gas storage tank, and a loss of NRC communications on November 10, 2022

(2) a licensed operator training evolution in the simulator including a high radiation release accident and a loss of emergency communications on December 1,

OTHER ACTIVITIES - BASELINE

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

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) ===

(1) October 1, 2021, through September 30, 2022

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

(1) October 1, 2021, through September 30, 2022

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) October 1, 2021, through September 30, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)

(1 Sample)

(1) October 1, 2021, through September 30, 2022 EP03: Alert and Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)

(1) October 1, 2021, through September 30, 2022

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in containment isolation valve failures that might be indicative of a more significant safety issue. No more than minor or significant adverse trends were identified.

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000382/2022-002-00, Operation Prohibited by Technical Specifications Due to Personnel Error (ADAMS Accession No. ML22133A248). The inspection conclusions associated with this LER are documented in this report under inspection results section

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===60854 - Preoperational Testing of an ISFSI Determine by direct observation and independent evaluation whether the licensee had developed, implemented, and evaluated preoperational testing activities to safely load spent fuel from site's spent fuel pool to the Independent Spent Fuel Storage Installation (ISFSI) and safely retrieve spent fuel from the ISFSI and transfer it back to the licensee's spent fuel pool.

Preoperational Testing of An ISFSI ===

(1) Waterford Steam Electric Station, Unit 3 is a 10 CFR Part 72 general licensee in accordance with 10 CFR 72.210. The licensee originally selected the Holtec International HI-STORM 100 Storage System (Certification of Compliance 72-1014)to store spent fuel at the site's ISFSI. In 2022, Waterford had elected to use the Holtec International HI-STORM FW Storage System (Certificate of Compliance 72-1032) to continue storing fuel at the ISFSI. The ISFSI contained 31 HI-STORM 100 casks holding 32 spent fuel assemblies and the future casks would be HI-STORM FW casks containing 37 spent fuel assemblies. On October 2-7 and December 12-13, 2022, inspectors performed onsite inspections to observe and evaluate pre-operational testing and training exercises. These operations are described in Condition 9 of the Certificate of Compliance and are required to be performed by a general licensee prior to the use of the system to store spent fuel assemblies. During the inspection period, inspectors specifically observed the following demonstrations that were successfully completed by the licensee:

movement of the FW cask from the fuel building to the ISFSI using the new vertical cask transporter (called the HI-TRAN)movement of the FW cask from inside the fuel building to outside the fuel building using the low profile transporter placement of the lid onto the FW cask using a mobile crane

===60856 - Review of 10 CFR 72.212(b) Evaluations Evaluate the licensee's program implementation for inclusion and use of the HI-STORM FW storage system into the site's existing 10 CFR Part 50 and Part 72 programs. The inspection scope included a review of the licensee's programs for heavy loads, emergency planning, fire protection, quality assurance, radiation protection, and site calculations to verify compliance with 10 CFR 72.212 requirements.

Review of 10 CFR 72.212(b) Evaluations ===

(1) On October 2-7, 2022, the NRC conducted an inspection of Waterford Steam Electric Stations 10 CFR Part 72 program implementation and 10 CFR 72.212 Report prior to the licensee's first loading campaign. Licensee calculations and evaluations were reviewed to verify compliance with requirements of the Certificate of Compliance 72-1032, License Amendment 5, and the HI-STORM FW Final Safety Analysis Report (FSAR), revision 8. The inspectors reviewed selected procedures, corrective action reports, and records to verify ISFSI operations were compliant with the Certificate's technical specifications, requirements in the FSAR, and NRC regulations. The Waterford ISFSI pad is sized to store 72 casks containing a mix of HI-STORM 100 storage casks and HI-STORM FW storage casks. At the time of the inspection, the ISFSI pad contained a total of 31 HI-STORM 100 storage casks and the licensee was in the process of performing dry runs to eventually load HI-STORM FW casks.

The following programs, procedures, and calculations were inspected:

site specific analysis that confirmed the licensee met the license conditions for flooding, tornados, lightning, blockage of inlet openings, off-normal temperature requirements, and snow and ice evaluation to confirm annual dose equivalent would meet 10 CFR 72.104 and 72.106 requirements evaluations under 10 CFR 50.59 for the ISFSI's impact on the reactor facility and compliance to site's heavy load program review of calculations for structural and seismic stability for the transfer cask on the fuel building crane and placement locations within the fuel building work orders and procedures that the fuel building's crane meets ASME B30.2 for load testing and annual maintenance requirements load testing and non-destructive testing records of special lifting devices used during loading operations fuel selection procedures to ensure fuel contents meet license conditions analyses to determine maximum weights placed on the cask handling crane during loading operations review of the site's fire and explosion hazards analysis for the ISFSI and walk-down of the heavy haul path and ISFSI to ensure all hazards had been identified and evaluated review of the site's quality assurance program, corrective action program, and implementing procedures for incorporation of FW system related activities review of the site's 72.48 program and associated reviews for identified changes since the last NRC ISFSI inspection performed in March

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71111.12 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Technical Specification 3.7.7, Controlled Ventilation Area System, requires that two independent controlled ventilation area system (CVAS) trains shall be operable. When one train is inoperable, the inoperable train shall be restored within 7 days, or the plant be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Contrary to the above, from July 2021 to March 2022, CVAS train B was inoperable for approximately 235 days with no action. Specifically, the inlet damper to emergency filtration unit B, HVR-304B, was incorrectly modified to be unable to fully open as required. On July 26, 2021, the licensee attempted to change the intermediate position of HVR-304B for corrective maintenance but instead modified the fully open position switch to be in the intermediate position. The result of this error is that the inlet damper would automatically open to the correct position on a safety injection actuation signal but would not be able to open further from a remote switch in the control room. The required ability to maintain -0.25 inches of water column pressure in the CVAS zones in the reactor auxiliary building during emergency conditions could have been challenged. On March 17, 2022, the licensee was performing troubleshooting for stroke-time testing from the closed to the intermediate position when a technician identified the modified fully open position switch. On March 18, 2022, the licensee corrected the fully open position to be in accordance with the HVR-304B data record.

Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Specifically, using Exhibit 3, Barrier Integrity Screening Questions, the inspectors determined that this finding is of very low safety significance (Green), because the finding only represented a degradation of the radiological barrier function provided for the auxiliary building.

Corrective Action References: CR-WF3-2022-01503

EXIT MEETINGS AND DEBRIEFS

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

On December 19, 2022, the inspectors presented the independent spent fuel storage installation dry runs, and 72.212 programs review inspection results to J. Ferrick, Site Vice President, and other members of the licensee staff.

On December 20, 2022, the inspectors presented the emergency preparedness program inspection results to D. Oertling, Regulatory and Performance Improvement Director, and other members of the licensee staff.

On January 17, 2023, the inspectors presented the integrated inspection results to J. Ferrick, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60854 Procedures DFS-004-003 MPC Loading at Waterford 3 for the HI-STORM FW 0

60854 Procedures DFS-004-004 MPC Processing at Waterford 3 for the HI-STORM FW 0

60854 Procedures DFS-004-005 MPC Transfer at Waterford 3 for the HI-STORM FW 0

60854 Procedures DFS-004-006 HI-STORM Movements at Waterford 3 for the HI-STORM FW 0

60854 Procedures DFS-004-008 Response to Abnormal Conditions at Waterford 3 for the HI- 0

STORM FW

60854 Procedures HI-2201100 Operations and Maintenance Manual for HI-TRAN 225 2

60856 Calculations HI-2043258, Identifying the Appropriate Convection Correlation in FLUENT 1

Project 5014 for Ventilation Air Flow in the HI-STORM System

60856 Calculations HI-2084192 Cask Handling Weights and Cask Handling Dimensions at 7

Waterford

60856 Calculations HI-2200993 ISFSI Site Boundary Dose Rate Calculations for Waterford 3 2

60856 Calculations HI-2210832 Thermal Evaluation of HI-STORM FW Version E1 During a 2

Flood Accident at Waterford 3

60856 Engineering 72.48-1574, Implementation of Holtec's HI-STORM FW System at 2

Evaluations Project No. 5014 Waterford Steam Electric Station Unit 3 (WF3)

60856 Engineering HI-2094301 Structural Analysis of Waterford ISFSI Pad 7

Evaluations

60856 Engineering HI-2094371 Evaluation of Fire and Explosion Hazards at Waterford 3 7

Evaluations

60856 Engineering HI-2210766 Waterford 3 Haul Path Underground Utility Evaluation 1

Evaluations

60856 Miscellaneous 10 CFR 72.212 10 CFR 72.212 Evaluation Report for HI-STORM FW System 0

Evaluation Report

60856 Miscellaneous CoC 72-1032 Holtec Certificate of Compliance 72-1032 Amendment

60856 Miscellaneous FSAR Holtec FW System Final Safety Analysis Report 8

60856 Miscellaneous HI-2094368 Structural Evaluation of the W3 Lift Yoke Extension 4

60856 Miscellaneous HI-2210901 Fuel Loading Plan for Waterford 3 NPP 3

60856 Procedures EN-LI-102 Corrective Action Program 47

60856 Procedures HPP-3130-0003 HI-TRAN 225 Version L Factory Acceptance Test Procedure 0

60856 Procedures UNT-007-008 Control of Heavy and Critical Loads 323

Inspection Type Designation Description or Title Revision or

Procedure Date

60856 Work Orders Entergy Waterford Inspect Crane per MM & ME Procedures 10/05/2022

52988198-01

71111.01 Procedures OP-901-521 Severe Weather and Flooding 340

71111.04 Corrective Action CR-WF3-YYYY- 2022-02008, 2022-02086, 2022-02102, 2022-02103,

Documents NNNN 2022-02104, 2022-02191, 2022-06443

71111.04 Engineering EC 93819 Operability Input for Corroded Rigid Restraints in Wet Cooling 09/14/2022

Evaluations Tower B

71111.04 Miscellaneous SD-HVR Reactor Auxiliary Building Heating, Ventilating, and Air 15

Conditioning System Description

71111.04 Miscellaneous W3-DBD-001 Safety Injection System 305

71111.04 Procedures OP-006-008 Transformer Operation 311

71111.04 Procedures OP-009-001 Containment Spray 307

71111.04 Procedures OP-009-002 Emergency Diesel Generator 360

71111.04 Procedures OP-009-008 Safety Injection System 48

71111.04 Work Orders 52968127

71111.05 Fire Plans NS-TB-005 +67 Turbine Building Operating Floor 2

71111.05 Fire Plans RAB 30-001 HP Office Area 9

71111.05 Fire Plans RAB 33-001 Shutdown Cooling Heat Exchanger Room A & B 11

71111.05 Fire Plans RAB 35-001 Safety Injection Pump Room B 10

71111.05 Fire Plans RAB 39-001 Reactor Auxiliary Building +35.00' Elevation 14

71111.05 Fire Plans ROOF E-001 Reactor Containment Building +46.00' Elevation 6

71111.06 Calculations ECM84-001 Charging Pump TDH 0

71111.06 Calculations ECM98-013 WCT Basin Flow to Condensate Storage Pool and EFW Pump 0

71111.06 Calculations MNQ3-5 Flooding Analysis Outside Containment 6

71111.06 Procedures OP-003-004 Condensate Makeup 317

71111.11Q Procedures EN-OP-115 Conduct of Operations 31

71111.11Q Procedures OP-100-014 TS and TRM Compliance 365

71111.11Q Procedures OP-901-502 Evacuation of the Control Room 41

71111.12 Corrective Action CR-WF3-YYYY- 2022-01221, 2022-01503, 2022-01538, 2022-7987,

Documents NNNN 2022-7990, 2022-7993, 2022-8001, 2022-8011, 2022-8020,

22-8029, 2022-8039

71111.12 Engineering EC 93699 Design Change for Temp Mod to Install a Jumper to 0

Changes Temporarily Disable the ESFAS Channel A Ground Alarm

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Miscellaneous TD-C490.0645 CE Engineered Safety Features Actuation System Auxiliary 3

Relay Cabinets Technical Manual

71111.12 Procedures EN-DC-203 Maintenance Rule Program 7

71111.12 Procedures EN-DC-204 Maintenance Rule Scope and Basis 8

71111.12 Procedures EN-DC-207 Maintenance Rule Periodic Assessment 6

71111.12 Procedures MM-003-046 Controlled Ventilation Area System Surveillance 311

71111.12 Procedures OP-002-004 Chilled Water System 324

71111.12 Work Orders 549086, 52969925, 52979213

71111.12 Work Orders 584860

71111.13 Corrective Action CR-WF3-YYYY- 2022-07178, 2022-07888

Documents NNNN

71111.13 Procedures EN-WM-104 On Line Risk Assessment 24

71111.13 Procedures MI-005-601 Primary Water Makeup Flow Calibration PMUIF0210 X 303

71111.13 Work Orders 52965535

71111.15 Corrective Action CR-WF3-2022- Condition Report 12/20/2022

Documents 07959

71111.15 Corrective Action CR-WF3-YYYY- 2022-07558, 2022-07625, 2022-07264, 2022-07959,

Documents NNNN 2022-07631, 2022-07682, 2022-7572, 2022-7593,

22-07959, 2022-07244

71111.18 Procedures SAMG-DPG-001 Diagnostic Process Guideline 0

71111.19 Corrective Action CR-WF3-YYYY- 2022-06852, 2022-07165, 2022-07893

Documents NNNN

71111.19 Drawings B424 Sht #160 ESFAS Auxiliary Relay Cab A Alarms 11

71111.19 Procedures OP-002-004 Chilled Water System 325

71111.19 Procedures OP-903-119 Secondary Auxiliaries Quarterly Inservice Tests 37

71111.19 Procedures OP-903-121 Safety Systems Quarterly IST Valve Tests 036

71111.19 Procedures STA-001-003 Containment Air Lock Overall Leakage Test and Door 302

Interlock Check

71111.19 Work Orders 52702730, 53010413, 588527

71111.22 Procedures OP-903-024 Reactor Coolant System Water Inventory Balance 26

71111.22 Procedures OP-903-030 Safety Injection Pump Operability Verification 041

71114.02 Corrective Action CR-WF3-YYYY- 2022-08077

Documents NNNN

Inspection Type Designation Description or Title Revision or

Procedure Date

Resulting from

Inspection

71114.02 Corrective Action CR-WF3-YYYY- 2022-08103

Documents NNNN

Resulting from

Inspection

71114.02 Miscellaneous Updated Alert/Notification System Design Report 8

71114.02 Procedures EPP-422 Siren and Helicopter Warning System Maintenance 15

71114.02 Procedures EPP-424 Siren Testing and Siren System Administrative Controls 21

71114.03 Corrective Action CR-WF3- 2022-08146

Documents

Resulting from

Inspection

71114.03 Miscellaneous ERO Callout Test Results from 4Q2020 through 3Q2022

71114.03 Miscellaneous Waterford 3 Station On-Shift Staffing Analysis Final Report 1

71114.03 Procedures EN-EP-310 Emergency Response Organization Notification System 11

71114.03 Procedures EN-EP-310 Emergency Response Organization Notification System

71114.03 Procedures EN-EP-603 Emergency Notifications 1

71114.03 Procedures EPP-462 Evaluation of ERO Callout Test 7

71114.04 Miscellaneous 10CFR50.54(Q)(3) Screening and Evaluation Form For 09/15/2022

EP-001-001 Revision 37

71114.04 Procedures DFS-007-003 Radiation Protection Requirements for Loading and Storage 9

HI-STORM

71114.04 Procedures EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 8

71114.04 Procedures EP-001-001 Recognition and Classification of Emergency Conditions 37

71114.04 Procedures EP-001-001 Recognition and Classification of Emergency Conditions 36

71114.05 Corrective Action CR-WF3- 2020-07050, 2020-07333, 2021-00022, 2021-00116,

Documents 2021-00390, 2021-01881, 2021-01937, 2021-02000,

21-02065, 2021-02123, 2021-02134, 2021-02170,

21-02171, 2021-02287, 2021-03065, 2021-03113,

21-03303, 2021-03312, 2021-03406, 2021-04514,

21-04678, 2021-04679, 2021-04689, 2021-04805,

21-04976, 2021-06324, 2021-06577, 2021-06708,

21-06995, 2022-00020, 2022-00283, 2022-00615,

Inspection Type Designation Description or Title Revision or

Procedure Date

22-00784, 2022-00805, 2022-00929, 2022-00930,

22-01327, 2022-01454, 2022-01516, 2022-01658,

22-03204, 2022-05019, 2022-05690, 2022-05698,

22-06104, 2022-06116, 2022-06255, 2022-06335,

22-06336, 2022-06510, 2022-06512

71114.05 Corrective Action CR-WF3-YYYY- 2022-08040

Documents NNNN

Resulting from

Inspection

71114.05 Miscellaneous WF3 09-13-22 Red Team Site Drill Report 10/10/2022

71114.05 Miscellaneous Control Room Emergency Breathing Air Drill Report 2021-1 04/30/2021

71114.05 Miscellaneous WF3 2022 1st Semi-Annual HP Drill Report 06/14/2022

71114.05 Miscellaneous Waterford 3 Steam Electric Station Emergency Plan 52

71114.05 Work Orders 568819, 573620, 567310

71114.06 Procedures EP-001-001 Recognition and Classification of Emergency Conditions 37

71114.06 Procedures OP-901-110 Pressurizer Level Control Malfunction 11

71114.06 Procedures OP-901-402 High Airborne Activity in Reactor Auxiliary Building 5

71151 Miscellaneous ANS Test Report Data 2021Q4 - 2022Q3

71151 Miscellaneous DEP PI Data 2021Q4 - 2022Q3

71151 Miscellaneous Quarterly Key ERO Member Drill Participation Data 2021Q4 -

22Q3

71151 Procedures EN-FAP-EP-005 Emergency Preparedness Performance Indicators 17

71152S Corrective Action CR-WF3-YYYY- 2022-1521, 2022-3165, 2022-3156, 2022-3713, 2022-4250,

Documents XXXX 2022-4727, 2022-5192, 2022-5583, 2022-5841, 2022-6141,

22-7184, 2022-8009

16