IR 05000382/2024002
| ML24215A277 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/08/2024 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Sullivan J Entergy Operations |
| References | |
| IR 2024002 | |
| Download: ML24215A277 (21) | |
Text
August 8, 2024
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - INTEGRATED INSPECTION REPORT 05000382/2024002
Dear Joseph Sullivan:
On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Waterford Steam Electric Station, Unit 3. On July 17, 2024, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. 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.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; 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 Reactor Projects Branch D Division of Operating Reactor Safety Docket No. 05000382 License No. NPF-38
Enclosure:
As stated
Inspection Report
Docket No.
05000382
License No.
Report No.
Enterprise Identifier:
I-2024-002-0007
Licensee:
Entergy Operations Inc.
Facility:
Waterford Steam Electric Station, Unit 3
Location:
Killona, LA 70057
Inspection Dates:
April 1, 2024, to June 30, 2024
Inspectors:
D. Childs, Resident Inspector
N. Greene, Senior Health Physicist
J. O'Donnell, Senior Health Physicist
A. Sanchez, Senior Project Engineer
C. Speer, Project Manager
Approved By:
John L. Dixon, Jr., Chief
Reactor 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.
List of Findings and Violations
Failure of Auxiliary Component Cooling Water Pump Motor a During Oil Sample Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000382/2024002-01 Open/Closed
[H.12] - Avoid Complacency 71152A The inspectors reviewed a self-revealed Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion V,
Instructions, Procedures, and Drawings, for failure to provide adequate guidance and instructions when taking an oil sample from an operating pump motor which caused a bearing failure and the pump to become inoperable.
Additional Tracking Items
None.
PLANT STATUS
Waterford, Unit 3, began the inspection period in shutdown in Mode 5 due a plant trip from a fire in main transformer B on March 21, 2024. The unit remained shutdown in Mode 5 until Waterford made the decision to start up the plant and operate with only main transformer A available; however, this constraint limited reactor power to 53 percent. Plant startup commenced on May 7, 2024, reaching Mode 1 on May 14, 2024, and 53 percent power on May 16, 2024. The unit remained in Mode 1 at 53 percent until down powering to 18 percent power and taking the main turbine offline to complete the replacement of main transformer B on June 9, 2024. The unit remained in Mode 1 at 18 percent power until replacement and testing of main transformer B was completed on June 14, 2024. Replacement transformer B is reduced in capacity and constrains reactor power to approximately 94 percent. Waterford, Unit 3, commenced raising power from 18 percent on June 14, 2024, and achieved 93 percent power on June 15, 2024. On June 16, 2024, an automatic trip occurred due to a lightning strike that caused an electrical perturbation that resulted in inadvertent trip signals being sent to the plants core protection calculators. The unit remained in Mode 3 until commencing plant startup on June 19, 2024, reaching Mode 1 on June 19, 2024, and 94 percent power on June 20, 2024. The unit remained at 94 percent power due to the reduced capacity of main transformer B for the remainder 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 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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the following systems: ultimate heat sink, emergency diesel generator system, and safety related switchgears on May 29, 2024.
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 April 9, 2024.
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 and 4160kv switchgear A while emergency diesel generator B was inoperable due to an emergent turbocharger issue on June 27, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the essential chilled water system on April 30, 2024.
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 areas ROOF E-001 and W-001, elevation +46.00' reactor containment building roof on April 15, 2024 (2)fire areas NS-TB-001 and -002, elevation +15.00' turbine building east and west on May 8, 2024 (3)fire area FHB-001, elevations -35.00' to +46.00' fuel handling building on June 3, 2024 (4)fire area RAB 20-001, elevation +21.00' reactor auxiliary building component cooling water pump AB on June 7, 2024
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) auxiliary component cooling water system trains A and B
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 startup activities on May 14, 2024.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during grid sync on June 16, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated operator training in the simulator for feedwater control and reactor trip override systems, and the new standing order to mitigate effects of an identified deficiency in the feedwater control system on April 17, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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)auxiliary component cooling water system train B after failure of the auxiliary component cooling pump B on May 24, 2024 (2)essential chilled water trains A and B following multiple issues challenging operability on June 13, 2024
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)yellow risk due to reactor coolant system drain down to mid-loop with fuel in the core to remove a seal on reactor coolant pump 2A on April 12, 2024 (2)yellow risk due to reactor coolant system drain down to mid-loop with fuel in the core to install a new seal on reactor coolant pump 2A on April 16, 2024 (3)elevated risk due to emergent turbocharger maintenance on emergency diesel generator B the week of June 24, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)safety related Rosemount transmitters operability determination after issues with environmental qualifications were identified through Entergy operating experience (2)excore nuclear instrument channel C operability determination after observed erratic behavior on May 14, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)temporary modification EC-0054128322 to provide a temporary offsite power source to the safety-related 4.16kv bus 2B due to the loss of startup transformer B on April 12, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage 25 activities from April 1 to May 14, 2024, which completes the partial sample documented in Waterford Inspection Report 05000382/2024001, section 71111.20.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (1 Sample)
(1)shield building ventilation system train A following replacement of a faulty contactor and performance of preventative maintenance activities associated with pressure and temperature loops on May 20, 2024
Surveillance Testing (IP Section 03.01) (5 Samples)
(1)local leak rate surveillance testing of reactor containment building equipment hatch on April 24, 2024 (2)emergency diesel generator A loaded run surveillance test on April 29, 2024 (3)safety injection actuation signal train B surveillance test on May 22, 2024 (4)safety injection actuation signal train A surveillance test on May 30, 2024 (5)containment spray pump A surveillance test on June 10, 2024
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
(1)safety injection tank 1A discharge check valve quarterly inservice testing on April 25, 2024 (2)emergency feedwater train A flow control valve quarterly inservice testing on June 3, 2024
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) Operational testing of the N diesel generator on May 15,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA)
(2)workers exiting the RCA at Unit 1 during a forced outage period
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)radiation work permit (RWP) 20240304, Forced Outage - Minor Maintenance Activities, task 1, to work on decontaminating the flash tank room below a contamination area, on the -4-foot elevation of the reactor auxiliary building (RAB)
(2)contamination controls for workers exiting the Unit 1 containment (3)radiation protection staff surveying items as workers exit the Unit 1 containment (e.g. camera and tools)
- (4) RWP 20240304, task 1, to work on checking high pressure safety injection valve leakage in a contaminated area outside of containment High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (4) HRA - process shield #1 in the radwaste solidification building
- (5) HRA - boric acid pre-concentration filter cubicles A and B on the -35-foot elevation of the RAB Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (1 Sample)
The inspectors evaluated the following internal dose assessments:
- (1) The inspectors reviewed the internal dose assessment records of a facial contamination.
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
- (1) The inspectors reviewed the records for three declared pregnant workers.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) April 1, 2023, through March 31, 2024
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) April 1, 2023, through March 31, 2024
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) April 1, 2023, through March 31, 2024
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) July 1, 2023, through March 31, 2024 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) July 1, 2023, through March 31, 2024
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)ground trucks used in resistance testing for safety related pumps providing inaccurate results on June 13, 2024 (2)auxiliary component cooling water pump B bearing failure on June 28,
INSPECTION RESULTS
Failure of Auxiliary Component Cooling Water Pump Motor A During Oil Sample Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000382/2024002-01 Open/Closed
[H.12] - Avoid Complacency 71152A The inspectors reviewed a self-revealed Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for failure to provide adequate guidance and instructions when taking an oil sample from an operating pump motor which caused a bearing failure and the pump to become inoperable.
Description:
On August 31, 2023, mechanics were attempting to collect an oil sample from the running pump motor bearing oil reservoir of auxiliary component cooling water (ACCW)pump A using a manual suction pump in accordance with OP-002-001, Auxiliary Component Cooling Water, revision 320. This had been a common, routine, licensee maintenance practice. During this time, the mechanics withdrew approximately 20-30 ml of the required 100 ml of oil from the motor oil reservoir, when the mechanics encountered problems with the manual suction pump. The mechanics left the jobsite to retrieve another pump. Work order 53035401 did not include any notes or cautions warning the mechanics about leaving the oil level lower than normal and they failed to recognize the need to add the amount of oil they had removed back into the oil reservoir.
While the mechanics were acquiring a new suction pump, motor bearing temperature started increasing steadily over the next 15 minutes. The main control room received a high vibration alarm at 9:17 a.m. on ACCW pump A inboard motor bearing. Operations tried to reset the alarm which did not reset. The main control room dispatched a non-licensed auxiliary operator to investigate. Upon arrival, a grumbling sound was heard that had not existed during normal rounds. A sheen of oil was observed on the inboard motor casing, pedestal, and floor. There was no visible oil level in the motor inboard bearing sight glass. Control room operators secured the pump at 9:33 a.m. Operators observed no coast down of the motor when the pump was secured, as it came to an immediate stop. The licensee entered the action statement for Technical Specification 3.7.3 declaring the ACCW A pump inoperable.
Following replacement of the pump motor, ACCW pump A was declared operable on September 4, 2023.
2 of fleet procedure EN-DC-310, Predictive Maintenance Program, revision 12, states that an individual trained in oil sampling techniques should obtain the oil sample, or adequate work instructions should be provided. Maintenance and operations training at each site in conjunction with Predictive Maintenance, determines the level of training and qualification required to perform oil sampling. Waterford made the decision to take all oil samples on running motors without recognizing that small reservoir motors were at higher risk for damage due to minimal oil being available to keep the bearing lubricated during the sampling process.
Section 4.1.3 of fleet procedure EN-MA-106, Planning, revision 6, states, that the planner is responsible for developing work packages in accordance with this procedure that ensure error-free maintenance and maintain design. Additionally, this procedure states that the planner is responsible for ensuring work instruction level of detail is consistent with the training and qualification program for the minimum qualified worker and/or skill of the craft.
Work order 53035401, used for acquiring the ACC pump A motor bearing oil sample, did not provide sufficient information to acquire the oil sample safely, without subjecting the pump motor to a potentially detrimental condition. With no information or cautions in the work order related to the concern of removing oil from the motor bearings for a prolonged period, the mechanics were unaware of the consequences. Removing a quantity of oil from the motor bearings without immediately replacing the oil was not recommended and could prove destructive to the motor bearings. Specifically, the mechanics did not recognize that they were to remove 100 ml from a 250 ml oil reservoir; they did not recognize that removing 20-30 ml of oil for a prolonged time of 15 minutes would attribute to bearing temperature rise and failure. Additionally, engineering, who controls the engineering owned oil sample Preventive Maintenance, failed to understand the risk of removing oil while the motor was running. Following consultation, the vendor recommended that the site stop taking oil samples while the equipment is running; instead, secure the equipment, immediately take the oil sample, replace the oil, then return to service.
Corrective Actions: Incorporate into work order documents to stop certain motors prior to taking future oil samples. Also, engineering will review and provide better guidance for taking oil samples. Training was performed on this event with the new requirement of securing certain motors prior to taking oil samples.
Corrective Action References: condition report CR-WF3-2023-15311
Performance Assessment:
Performance Deficiency: The inspectors determined that the failure to have adequate instructions in the work order for withdrawing an oil sample from an operating pump motor was a performance deficiency. Specifically, the licensee failed to provide work instructions that appropriately indicated the risks involved with removing oil from an operating safety related pump motor bearing or appropriate actions to mitigate that risk.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the ACCW pump motor failed due to the licensee not providing sufficient training or instructions to adequately take an oil sample from an operating pump motor.
Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined the finding was of very low safety significance (Green)because the finding was a deficiency affecting the design or qualification of a mitigating structure, system, or component (SSC) and the SSC maintained its operability or functionality.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the licensee failed to consider the potential impacts of removing oil from the bearing of running pump for an extended period.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, states, Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Contrary to the above, prior to August 31, 2023, instructions, procedures, or drawings did not include appropriate quantitative or qualitative guidance to safely accomplish the acquisition of an oil sample from a running, safety related motor, without causing the motor to fail.
Specifically, the skill of the craft training, and instructional guidance in work order 53035401 for safely removing an oil sample from a running, operational, safety related motor was inadequate to prevent failure of the motor.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Minor Performance Deficiency 71152A Minor Performance Deficiency Minor Performance Deficiency: The inspectors identified a minor performance deficiency for failure to provide adequate induction motor testing procedures. Specifically, licensee procedures ME-004-330, 4kV Induction Motor Testing, and ME-004-340, 7kV Induction Motor Testing, did not include resistance checks on ground trucks prior to use for motor testing. It was found that the ground trucks used in resistance testing were providing low resistance values which made test results appear worse than actual. For example, component cooling water pump B degraded from 698 MOhms to 69 MOhms between the 2019 to 2022 tests.
Testing results still met minimum acceptance criteria; however, these results make the pumps insulation appear to be degrading faster than actuality in the Motor Component Monitoring Program (i.e., conservatively).
Screening: The inspectors determined the performance deficiency was minor. The inspectors determined the performance deficiency to be minor because the inaccurate resistance values provided were conservative in nature and made pump insulation appear to be degrading faster than actuality; therefore, there were no instances for which actual insulation degradation remained undetected.
Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. This failure to provide an adequate procedure constitutes a minor performance deficiency that is not subject to enforcement action in accordance with the NRCs Enforcement Policy. The licensee generated condition report CR-WF3-2023-13327 to address this issue in their corrective action program.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 10, 2024, the inspectors presented the occupational radiation safety inspection results to Joseph Sullivan, Site Vice President, and other members of the licensee staff.
- On July 17, 2024, the inspectors presented the integrated inspection results to Joseph Sullivan, Site Vice President, and other members of the licensee staff
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-02759
Miscellaneous
WT-WF3-2023-
2011757
24 Summer Reliability Plan
07/17/2023
Procedures
EN-FAP-WM-016
Seasonal Reliability
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-01046, 2023-18122, 2023-17856, 2023-17628
Procedures
OP-002-004
Chilled Water System
25
Procedures
OP-009-002
360
Fire Plans
FHB-001
Fuel Handling Building
Fire Plans
NS-TB-001
Turbine Building Ground Floor +15.00 East
Fire Plans
NS-TB-002
Turbine Building Ground Floor +15.00 West
Fire Plans
RAB 20-001
Component Cooling Water Pump A/B
Fire Plans
ROOF E-001
Reactor Containment Building +46.00' Elevation
Fire Plans
ROOF W-001
Reactor Containment Building +46.00' Elevation
Engineering
Changes
Relaxation of Thermal Performance Testing Frequency for
ACCW System per GL 89-13 Requirements
Miscellaneous
ER-W3-2001-
25-000
CCW Monitoring Plan
Miscellaneous
ER-W3-2001-
25-001
CCW Monitoring Plan Clarifications
Procedures
CE-002-003
Maintaining Auxiliary Component Cooling Water Chemistry
2
Procedures
OP-003-033
Main Feedwater
330
Procedures
OP-003-035
313
Procedures
OP-010-003
Plant Startup
366
Procedures
OP-901-521
Severe Weather and Flooding
343
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-01345, 2024-01290, 2024-01083, 2024-01905,
24-00219, 2024-00092, 2023-17500, 2023-17164,
23-017150
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
23-17150, 2023-17164, 2023-17500, 2024-01743
Procedures
Maintenance Rule Monitoring
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-01755, 2024-02020
Procedures
Nuclear Risk Management Process
Procedures
Protected Equipment Postings
Procedures
PLG-009-014
Control of Outages
21
Work Orders
54127178, 54127227, 54127271
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-01097, 2024-01706, 2024-00994
Miscellaneous
LPL-EQA-8.1A
Environmental Qualification Assessment on Rosemount
Transmitters Type 1152 Used in the Waterford SES Unit No.
Miscellaneous
LPL-EQMI-08.01
Rosemount Model 1153 Series A, B & D, 1154 & 1154
Series H Transmitters and 1159 Remote Seals
Miscellaneous
TD-R369.0140
Rosemount 1153 Series B Aphaline Nuclear Pressure
Transmitter Reference Manual 4302
Miscellaneous
W3-DBD-012
Design Basis Document Plant Protection System
Procedures
OP-500-009
Control Room Cabinet K
Engineering
Changes
Temporary Power 4AB to 2B Bus
Engineering
Changes
Temp Power Source for 4.16kv bus 2B
Engineering
Changes
FCR-54132262
Testing Requirement Changes to EC-54128322
Procedures
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-02319
Miscellaneous
FIG-001
FLEX Implementing Guide
Procedures
OP-009-002
360
Procedures
OP-903-029
Safety Injection Actuation Signal Test
Procedures
OP-903-033
Cold Shutdown IST Valve Tests
Procedures
OP-903-069
Emergency Diesel Generator and Subgroup Relay
Operability Verification
27
Procedures
OP-903-121
Safety Systems Quarterly IST Valve Tests
Procedures
STA-001-004
20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
54136059, 54127437, 54127242, 54081318, 53019766,
54122234
ALARA Plans
RWP 20230705
Refuel 25 - Reassembly of Reactor Head and Associated
Work Activities including Staging/Destaging of Equipment
01/24/2024
Corrective Action
Documents
CR-WF3-YYYY-
XXXXX
22-07357, 2023-16223, 2023-16474, 2023-16822,
23-17095, 2023-17230, 2023-17690, 2023-17984,
23-18161, 2023-18463, 2024-00699
Miscellaneous
High Radiation Area, Locked High Radiation Area, & Very
High Radiation Area Weekly Checklist
05/12/2024
Miscellaneous
Personnel Contamination Events Log
05/06/2024
Procedures
Special Nuclear Material Control
Procedures
PWR Control of Miscellaneous Material in the Spent Fuel
Pool
Procedures
Radiation Worker Expectations
Procedures
Access Control for Radiologically Controlled Areas
Procedures
Radiological Control
Procedures
Radiological Survey Documentation
Procedures
Radiation Protection Posting
Procedures
Hot Spot Program
Procedures
ALARA Program
Procedures
Radioactive Material Control
Procedures
Alpha Monitoring
Procedures
Air Sampling
Procedures
UNT-005-014
Offsite Dose Calculation Manual
309
Radiation
Surveys
-35 Reactor Auxiliary Building Spent Resin Tank Pump
Room, Waste Condensate IX
03/13/2024
Radiation
Surveys
-4 Reactor Containment Building
03/26/2024
Radiation
Surveys
-11 Reactor Containment Building
03/26/2024
Radiation
Surveys
Reactor Auxiliary Building -35, Boric Acid Pre-Concentrator
Filters
04/01/2024
Radiation
Surveys
Radwaste Solidification Building
04/05/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
Monthly Survey of +46 Fuel Handling Building
04/05/2024
Radiation
Surveys
-4 Reactor Auxiliary Building
05/01/2024
Radiation
Surveys
-4 Reactor Auxiliary Building Flash Tank/Purification Filter
Area Monthly Survey
05/03/2024
Radiation
Surveys
WF3-AS-101823-
275
+46 Unit 1 Reactor Containment Building Upper Cavity
10/18/2023
Radiation
Surveys
WF3-AS-101823-
276
+46 Unit 1 Reactor Containment Building Cavity, General
Area, Disassembly
10/18/2023
Radiation
Surveys
WF3-AS-110623-
0788
-11 Reactor Containment Building, Work on Reactor Coolant
Pump Heat Exchanger
11/06/2023
Radiation Work
Permits (RWPs)
230510
RF25 - Install/Remove Steam Generator Nozzle Dams
Verification and Closeout
Radiation Work
Permits (RWPs)
230515
Remove/Install RCP 1A Motor, RCP Seal, Rotating Baffle,
RCP Heat Exchanger
Radiation Work
Permits (RWPs)
240011
Restricted Tours, Inspections, and Work Activities in the
Radiologically Controlled Area (RCA)
Radiation Work
Permits (RWPs)
240306
Forced Outage - Minor Maintenance Activities (including
scaffold and insulation), Operation task, Walkdowns,
Surveillances and Inspections, Sampling, RP,
Processing/Shipping, Various Decon
Self-Assessments LO-WLO-2022-
00086 CA-00001
Radiological Hazard Assessment and Exposure Controls
2/06/2024
ALARA Plans
23-0515 Post
Job Review
Removal/Install RCP 1A Motor, RCP Seal, Rotating Baffle,
RCP Heat Exchanger
04/29/2024
ALARA Plans
23-0610 In
Progress Review
Refuel 25 - Erect/Dismantle Scaffolding in the Reactor
Containment Building
11/08/2023
ALARA Plans
23-0708 Post
Job Review
Refuel 25 - Heater Junction Thermocouple (2) and Stinger
(3) Replacement Work Activities
11/10/2023
ALARA Plans
23-2027
Station 5-Year Exposure Reduction Plan
2/01/2022
Calibration
Records
FastScan
Calibration of the Mirion Fast Scan WBC System
04/12/2024
Corrective Action
CR-WF3-YYYY-
23-15263, 2023-16223, 2023-16822, 2023-16873,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
XXXXX
23-16898, 2023-17095, 2023-17324, 2023-17598,
23-017690, 2023-17787, 2023-17796, 2023-017802,
23-17861, 2024-01751, 2024-01912
Corrective Action
Documents
Resulting from
Inspection
CR-HQN-YYYY-
XXXXX
24-00572, 2024-02504
Engineering
Evaluations
WF-AS-110123-
0634
Dose Assessment for an Uptake on 11/01/2023
11/13/2023
Miscellaneous
Personnel Contamination Log
23
Miscellaneous
100518-0
NVLAP Accreditation Certificate
01/01/2024
Miscellaneous
23
DLR Monitoring Period Established Background
04/24/2024
Miscellaneous
L103525
Report of Analysis/Certificate of Conformance
2/29/2023
Miscellaneous
WF3-RPT-2-001
2 Dry Fuel Storage Neutron Dosimetry Evaluation
01/13/2020
Miscellaneous
WF3-RPT-20-002
Waterford 3 2019 Fourth Quarter Background Subtraction
Study
04/27/2020
Miscellaneous
WF3-RPT-21-004
Waterford 3 Plant Characterization
11/04/2021
Procedures
ALARA Program
Procedures
Alpha Monitoring
Procedures
Air Sampling
Procedures
Conduct of Radiation Protection
Procedures
Dosimetry Administration5
Procedures
Personnel Monitoring
Procedures
Dose Assessment
Procedures
Special Monitoring Requirements
Procedures
Prenatal Monitoring
Procedures
Whole Body Counting / In-Vitro Bioassay
Procedures
Selection, Issue and Use of Respiratory Protection
Equipment
Radiation
Surveys
RF25
RF 25 Post Outage ALARA Report
Radiation
Surveys
WF3-AS-103123-
0579
Particulate Sample Report
10/31/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
WF3-AS-103123-
0580
Lapel Sample Report
10/31/2023
Radiation
Surveys
WF3-AS-103123-
0581
Lapel Sample Report
10/31/2023
Radiation
Surveys
WF3-AS-110123-
0637
Particulate Sample Report
11/01/2023
Radiation
Surveys
WF3-AS-110123-
0638
Lapel Sample Report
11/01/2023
Radiation
Surveys
WF3-AS-110123-
0643
Particulate Sample Report
11/01/2023
Radiation
Surveys
WF3-AS-110123-
0644
Lapel Sample Report
11/01/2023
Radiation
Surveys
WF3-AS-110123-
0646
Lapel Sample Report
11/01/2023
Radiation Work
Permits (RWPs)
23-0511 Post
Job Review
RF25 Perform Eddy Current Work/Tube Plugging
04/15/2024
Self-Assessments LO-WLO-2022-
00086-00001
IP 71124.04 Occupational Dose Assessment
2/01/2024
71151
Miscellaneous
Annual Radioactive Effluent Release Report (ARERR) 2022
with Revised ODCM
04/27/2023
71151
Procedures
Response to Contaminated Spills/Leaks
Corrective Action
Documents
CR-HQN-YYYY-
NNNN
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
23-13327, 2023-14263, 2023-17142, 2023-17522,
23-17528, 2023-17934, 2023-18508, 2024-00276,
24-01357, 2008-00421, 2023-15311
Engineering
Changes
LPSI A - Input to Operability
Procedures
Predictive Maintenance Program
Procedures
Predictive Maintenance Program
Procedures
EN-FAP-LI-001
Performance Improvement Review Group (PRG) Process
Procedures
Work Order Generation, Screening and Classification
Procedures
Training Material Title: Lubrication
Procedures
ME-004-330
4kV Induction Motor Maintenance
307
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
ME-004-330
4kV Induction Motor Maintenance
306
Procedures
ME-004-340
7kV Induction Motor Maintenance
307
Procedures
ME-004-340
7kV Induction Motor Maintenance
306
Procedures
UNT-005-007
Plant Lubrication Program
307
Work Orders
53030774, 53034053, 54058512, 584014, 54047113,
53035401-01, 54046166-29