IR 05000382/2022004
| 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, 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:
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
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 Technical Specifications Due to Personnel Error 71153 Closed
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.
REACTOR SAFETY
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
Procedure
Type
Designation
Description or Title
Revision or
Date
60854
Procedures
DFS-004-003
MPC Loading at Waterford 3 for the HI-STORM FW
60854
Procedures
DFS-004-004
MPC Processing at Waterford 3 for the HI-STORM FW
60854
Procedures
DFS-004-005
MPC Transfer at Waterford 3 for the HI-STORM FW
60854
Procedures
DFS-004-006
HI-STORM Movements at Waterford 3 for the HI-STORM FW
60854
Procedures
DFS-004-008
Response to Abnormal Conditions at Waterford 3 for the HI-
60854
Procedures
HI-2201100
Operations and Maintenance Manual for HI-TRAN 225
60856
Calculations
HI-2043258,
Project 5014
Identifying the Appropriate Convection Correlation in FLUENT
for Ventilation Air Flow in the HI-STORM System
60856
Calculations
HI-2084192
Cask Handling Weights and Cask Handling Dimensions at
Waterford
60856
Calculations
HI-2200993
ISFSI Site Boundary Dose Rate Calculations for Waterford 3
60856
Calculations
HI-2210832
Thermal Evaluation of HI-STORM FW Version E1 During a
Flood Accident at Waterford 3
60856
Engineering
Evaluations
2.48-1574,
Project No. 5014
Implementation of Holtec's HI-STORM FW System at
Waterford Steam Electric Station Unit 3 (WF3)
60856
Engineering
Evaluations
HI-2094301
Structural Analysis of Waterford ISFSI Pad
60856
Engineering
Evaluations
HI-2094371
Evaluation of Fire and Explosion Hazards at Waterford 3
60856
Engineering
Evaluations
HI-2210766
Waterford 3 Haul Path Underground Utility Evaluation
60856
Miscellaneous
CFR 72.212
Evaluation Report
CFR 72.212 Evaluation Report for HI-STORM FW System
60856
Miscellaneous
CoC 72-1032
Holtec Certificate of Compliance 72-1032
Amendment
60856
Miscellaneous
Holtec FW System Final Safety Analysis Report
60856
Miscellaneous
HI-2094368
Structural Evaluation of the W3 Lift Yoke Extension
60856
Miscellaneous
HI-2210901
Fuel Loading Plan for Waterford 3 NPP
60856
Procedures
Corrective Action Program
60856
Procedures
HPP-3130-0003
HI-TRAN 225 Version L Factory Acceptance Test Procedure
60856
Procedures
UNT-007-008
Control of Heavy and Critical Loads
23
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60856
Work Orders
Entergy Waterford
52988198-01
Inspect Crane per MM & ME Procedures
10/05/2022
Procedures
OP-901-521
Severe Weather and Flooding
340
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-02008, 2022-02086, 2022-02102, 2022-02103,
22-02104, 2022-02191, 2022-06443
Engineering
Evaluations
Operability Input for Corroded Rigid Restraints in Wet Cooling
Tower B
09/14/2022
Miscellaneous
SD-HVR
Reactor Auxiliary Building Heating, Ventilating, and Air
Conditioning System Description
Miscellaneous
W3-DBD-001
Safety Injection System
305
Procedures
OP-006-008
Transformer Operation
311
Procedures
OP-009-001
307
Procedures
OP-009-002
360
Procedures
OP-009-008
Safety Injection System
Work Orders
2968127
Fire Plans
NS-TB-005
+67 Turbine Building Operating Floor
Fire Plans
RAB 30-001
HP Office Area
Fire Plans
RAB 33-001
Shutdown Cooling Heat Exchanger Room A & B
Fire Plans
RAB 35-001
Safety Injection Pump Room B
Fire Plans
RAB 39-001
Reactor Auxiliary Building +35.00' Elevation
Fire Plans
ROOF E-001
Reactor Containment Building +46.00' Elevation
Calculations
ECM84-001
Charging Pump TDH
Calculations
ECM98-013
WCT Basin Flow to Condensate Storage Pool and EFW Pump
Calculations
MNQ3-5
Flooding Analysis Outside Containment
Procedures
OP-003-004
Condensate Makeup
317
Procedures
Conduct of Operations
Procedures
OP-100-014
TS and TRM Compliance
365
Procedures
OP-901-502
Evacuation of the Control Room
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-01221, 2022-01503, 2022-01538, 2022-7987,
22-7990, 2022-7993, 2022-8001, 2022-8011, 2022-8020,
22-8029, 2022-8039
Engineering
Changes
Design Change for Temp Mod to Install a Jumper to
Temporarily Disable the ESFAS Channel A Ground Alarm
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
TD-C490.0645
CE Engineered Safety Features Actuation System Auxiliary
Relay Cabinets Technical Manual
Procedures
Procedures
Maintenance Rule Scope and Basis
Procedures
Maintenance Rule Periodic Assessment
Procedures
MM-003-046
Controlled Ventilation Area System Surveillance
311
Procedures
OP-002-004
Chilled Water System
24
Work Orders
549086, 52969925, 52979213
Work Orders
584860
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-07178, 2022-07888
Procedures
On Line Risk Assessment
Procedures
MI-005-601
Primary Water Makeup Flow Calibration PMUIF0210 X
303
Work Orders
2965535
Corrective Action
Documents
CR-WF3-2022-
07959
Condition Report
2/20/2022
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-07558, 2022-07625, 2022-07264, 2022-07959,
22-07631, 2022-07682, 2022-7572, 2022-7593,
22-07959, 2022-07244
Procedures
SAMG-DPG-001
Diagnostic Process Guideline
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-06852, 2022-07165, 2022-07893
Drawings
B424 Sht #160
ESFAS Auxiliary Relay Cab A Alarms
Procedures
OP-002-004
Chilled Water System
25
Procedures
OP-903-119
Secondary Auxiliaries Quarterly Inservice Tests
Procedures
OP-903-121
Safety Systems Quarterly IST Valve Tests
036
Procedures
STA-001-003
Containment Air Lock Overall Leakage Test and Door
Interlock Check
2
Work Orders
2702730, 53010413, 588527
Procedures
OP-903-024
Reactor Coolant System Water Inventory Balance
Procedures
OP-903-030
Safety Injection Pump Operability Verification
041
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-08077
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Corrective Action
Documents
Resulting from
Inspection
CR-WF3-YYYY-
NNNN
22-08103
Miscellaneous
Updated Alert/Notification System Design Report
Procedures
EPP-422
Siren and Helicopter Warning System Maintenance
Procedures
EPP-424
Siren Testing and Siren System Administrative Controls
Corrective Action
Documents
Resulting from
Inspection
CR-WF3-
22-08146
Miscellaneous
ERO Callout Test Results from 4Q2020 through 3Q2022
Miscellaneous
Waterford 3 Station On-Shift Staffing Analysis Final Report
Procedures
Emergency Response Organization Notification System
Procedures
Emergency Response Organization Notification System
Procedures
Emergency Notifications
Procedures
EPP-462
Evaluation of ERO Callout Test
Miscellaneous
10CFR50.54(Q)(3) Screening and Evaluation Form For
EP-001-001 Revision 37
09/15/2022
Procedures
DFS-007-003
Radiation Protection Requirements for Loading and Storage
HI-STORM
Procedures
Emergency Planning 10CFR50.54(q) Review Program
Procedures
Recognition and Classification of Emergency Conditions
Procedures
Recognition and Classification of Emergency Conditions
Corrective Action
Documents
CR-WF3-
20-07050, 2020-07333, 2021-00022, 2021-00116,
21-00390, 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
Procedure
Type
Designation
Description or Title
Revision or
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
Corrective Action
Documents
Resulting from
Inspection
CR-WF3-YYYY-
NNNN
22-08040
Miscellaneous
WF3 09-13-22 Red Team Site Drill Report
10/10/2022
Miscellaneous
Control Room Emergency Breathing Air Drill Report 2021-1
04/30/2021
Miscellaneous
WF3 2022 1st Semi-Annual HP Drill Report
06/14/2022
Miscellaneous
Waterford 3 Steam Electric Station Emergency Plan
Work Orders
568819, 573620, 567310
Procedures
Recognition and Classification of Emergency Conditions
Procedures
OP-901-110
Pressurizer Level Control Malfunction
Procedures
OP-901-402
High Airborne Activity in Reactor Auxiliary Building
71151
Miscellaneous
ANS Test Report Data 2021Q4 - 2022Q3
71151
Miscellaneous
71151
Miscellaneous
Quarterly Key ERO Member Drill Participation Data 2021Q4 -
22Q3
71151
Procedures
EN-FAP-EP-005
Emergency Preparedness Performance Indicators
Corrective Action
Documents
CR-WF3-YYYY-
XXXX
22-1521, 2022-3165, 2022-3156, 2022-3713, 2022-4250,
22-4727, 2022-5192, 2022-5583, 2022-5841, 2022-6141,
22-7184, 2022-8009