IR 05000382/2024001
| ML24122A707 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/06/2024 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Sullivan J Entergy Operations |
| References | |
| IR 2024001 | |
| Download: ML24122A707 (16) | |
Text
May 06, 2024
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - INTEGRATED INSPECTION REPORT 05000382/2024001
Dear Joseph Sullivan:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Waterford Steam Electric Station, Unit 3. On April 17, 2024, the NRC inspectors discussed the results of this inspection with David Oertling, General Manager of Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, John L. Dixon, Jr, Chief Reactor Projects Branch D Division of Operating Reactor Safety Signed by Dixon, John on 05/06/24 Docket No. 05000382 License No. NPF-38
Enclosure:
As stated
Inspection Report
Docket Number:
05000382
License Number:
Report Number:
Enterprise Identifier:
I-2024-001-0005
Licensee:
Entergy Operations, Inc.
Facility:
Waterford Steam Electric Station, Unit 3
Location:
Killona, LA 70057
Inspection Dates:
January 1, 2024, to March 31, 2024
Inspectors:
D. Childs, Senior Resident Inspector
R. Kopriva, Senior Project Engineer
A. Patz, Executive Technical Assistant
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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000382/2023-002-00 Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in Containment 71153 Closed
PLANT STATUS
Waterford, Unit 3, began the inspection period shutdown for refueling outage 25 in Mode 4 and heated up to Mode 3 for turbine generator testing on January 1, 2024. After the completion of testing the unit was returned to Mode 5 on January 4, 2024. The unit remained shut down until beginning plant startup on January 23, 2024, reaching 100 percent power on February 9, 2024.
The unit was manually tripped offline on March 16, 2024, after an equipment failure caused main feedwater isolation valve 2 to start closing. After replacement of the failed equipment, the unit was returned to 98 percent power on March 21, 2024. Later that same day the reactor automatically tripped due to a partial loss of offsite power from a fire in main transformer B. The unit entered Mode 5 on March 22, 2024, and remained in Mode 5 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
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 January 8, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)auxiliary component cooling water system train A while train B was out of service for planned maintenance on February 15, 2024 (2)emergency diesel generator A while emergency diesel generator B was supplying power to the B safety bus during an unplanned outage on March 27, 2024
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 areas RAB 3A-002, elevation +46.00' reactor auxiliary building vestibule, and RAB 3A-004, elevations -4.00' to +7.00' to +46.00' reactor auxiliary building heating, ventilating, and air conditioning plenum on January 3, 2024 (2)fire area RAB 8A-001, elevation +21.00' switchgear room A on January 25, 2024 (3)fire area RAB 7-001, elevation +35.00' reactor auxiliary building relay room on February 29, 2024 (4)fire area RAB 2-001, elevation +46.00' reactor auxiliary building H&V mechanical room on March 1, 2024 (5)fire areas RAB 11-001,12-001, and 13-001, elevation +21.00' reactor auxiliary building battery rooms 3A, 3B, and 3AB on March 5, 2024
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in zone 5 hallway/open rooms on -35' elevation of the reactor auxiliary building.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during ascension to criticality on February 1, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated simulator training for plant startup following refueling outage on January 18, 2024.
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)emergency diesel generator A following planned maintenance to replace the hydraulic governor on January 11, 2024 (2)main steam isolation valve 1 after failed valve stroke time test on February 27, 2024 (3)control room habitability after smoke test failures on March 28, 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 planned outage of auxiliary component cooling water system train A and safety related 4160 Vac bus swap of 3AB/31AB from train A to train B from February 14-15, 2024 (2)yellow risk due to heavy lift work in the Waterford 3 switchyard concurrent with an unplanned outage of emergency diesel generator B from February 22-23, 2024 (3)yellow risk due to lite lift work in the Waterford 3 transformer yard concurrent with a planned outage of high-pressure safety injection pump B from March 13-14, 2024
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)diesel driven fire pumps 1 and 2 functionality assessment due to identification of failed radiator preheaters on January 22, 2024 (2)control room envelope operability determination due to the failure of door 261 on February 1, 2024 (3)emergency diesel generator B operability determination due to the identification of a jacket water system leak on the turbo charger piping on February 21, 2024 (4)emergency diesel generator B operability determination due to the identification of an oil leak upstream of the intake silencer on March 11, 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)engineered safety feature actuation system cabinet permanent modification after identification that fire seals were not installed in conduits on February 28, 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 January 1, 2024, to February 5, 2024, which completes the partial sample documented in Waterford Inspection Report 05000382/2023004, Section 71111.20.
(2)
(Partial)
The inspectors evaluated forced outage activities from March 22, 2024, to the end of the inspection period, March 31, 2024. This sample will be closed in a future inspection report.
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) (3 Samples)
(1)turbine driven emergency feedwater pump AB after overhaul during refueling outage on January 2, 2024 (2)emergency diesel generator A after replacement of the governor on January 11, 2024 (3)auxiliary component cooling water system train A after planned maintenance on February 15, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)
(2)plant protection system reactor trip on turbine trip functional testing on core protection calculators A, B, C, and D on February 7, 2024 plant protection system channels A, B, C, and D functional test on March 7, 2024 (3)containment spray pump B operability test on March 12, 2024 (4)atmospheric dump valves 1 and 2 surveillance testing prior to plant startup on March 18, 2024
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
(1)emergency feedwater system train A flow control and isolation valves, quarterly in-service testing on March 4, 2024 (2)component cooling water pump AB on March 13,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) January 1, 2023, through December 31, 2023 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) January 1, 2023, through December 31, 2023 IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03)
- (1) January 1, 2023, through December 31, 2023 (2)
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)reactor coolant system leak in an instrument tubing line downstream of reactor coolant pump 1B differential pressure transmitter isolation valve, RC-114B, that resulted in an unplanned shutdown for repairs on February 8, 2024
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
- (1) The inspectors evaluated the licensees response to an unplanned closure of main steam isolation valve 2 and main feed isolation valve 2 and licensees performance on March 16, 2024.
- (2) The inspectors evaluated the licensees response to a partial loss of offsite power from a fire in main transformer B and licensees performance on March 21, 2024.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000382/2023-002-00, Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in Containment (ADAMS Accession No. ML23129A791). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency or violation of NRC requirements was identified. This LER is Closed.
Reporting (IP Section 03.05) (1 Sample)
The inspectors evaluated the following licensee event notifications (EN):
- (1) EN 57042, Notification of Unusual Event Due to Fire in the Protected Area. This EN was submitted and subsequently retracted by licensee correspondence titled Retraction of Notice of Unusual Event on 03/26/24 at 1721 from L. Brown to K. Cotton, dated March 26, 2024 (Updated EN 57042). No performance deficiency or violation of NRC requirements was identified.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 17, 2024, the inspectors presented the integrated inspection results to David Oertling, General Manager of Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-901-521
Severe Weather and Flooding
343
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-00145, 2024-00650, 2023-14867, 2023-15951
Procedures
OP-002-001
Auxiliary Component Cooling Water
20
Procedures
OP-009-002
360
Fire Plans
RAB 11-001
Battery Room 3B
Fire Plans
RAB 12-001
Battery Room 3AB
Fire Plans
RAB 13-001
Battery Room 3A
Fire Plans
RAB 2-001
H&V Mechanical Room Reactor Auxiliary Building +46.00'
Elevation
Fire Plans
Reactor Auxiliary Building -4.00' to +7.00' to +46.00'
Elevations HVAC Plenum
Fire Plans
RAB 7-001
Reactor Auxiliary Building +35.00' Elevation Relay Room
Fire Plans
Switchgear Room A
Fire Plans
RAB-3A-002
Reactor Auxiliary Building +46.00 Elevation Vestibule
Calculations
MNQ3-5
Flooding Analysis Outside of Containment
Procedures
NE-002-002
Variable Taverage Test
Procedures
OP-005-007
Main Turbine and Generator
313
Procedures
OP-010-003
Plant Startup
366
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
22-02759, 2022-05580, 2022-06601, 2022-08221,
23-01057, 2023-13241, 2023-14864, 2023-16255
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
14603, 14604, 14606
Engineering
Changes
Relaxation of Thermal Performance Testing Frequency for
01/31/2024
Procedures
CEP-IST-004
Standard on Inservice Testing
313
Procedures
Control Room Habitability Program
Procedures
Maintenance Rule Monitoring
Procedures
MM-006-106
Plant Door Maintenance
335
Procedures
OP-903-033
Cold Shutdown IST Valve Testing
Procedures
PE-005-042
2
Work Orders
536720, 54054584
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
24-01017
Procedures
Protected Equipment Postings
Procedures
On Line Risk Assessment
Procedures
OI-037-000
Operations Risk Assessment Guideline
21
Work Orders
53025665, 54091298, 54123122
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
23-13488, 2024-00265, 2024-00266, 2023-14604,
23-14606, 2024-01017
Engineering
Changes
NFPA 20, 1972 Edition "Standard for the Installation of
Centrifugal Fire Pumps" Code Compliance Evaluation
Engineering Report (Report WF3-FP-10-00015)
07/13/2011
Miscellaneous
Updated Final Safety Analysis Report
371
Miscellaneous
TD-D302.0015
Detroit Diesel Inline Series 71 Service Manual
Miscellaneous
W3-DBD-002
Emergency Diesel Generator & Automatic Load Sequencer
306
Miscellaneous
W3-DBD-018
Fire Protection Upper-Level Design Basis Document
Procedures
Control Room Habitability Program
Procedures
Operability Determination Process
Procedures
PE-005-0042
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
23-15383, 2023-15990, 2023-17399, 2023-17534
Engineering
Changes
54083578
Fire Seals in ESFAS ARC A & B for Bay Separation
Engineering
Evaluations
C-CD-9210
Failure Analysis - Auxiliary Relay Cabinet - ESFAS Cycling
Relays
07/24/1984
Miscellaneous
W3-DBD-018
Fire Protection Upper-Level Design Basis Document
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
23-17095, 2023-17112, 2023-17122
Procedures
Fatigue Management Program
Corrective Action
Documents
CR-WF3-YYYY-
XXXX
24-01385
Procedures
ME-004-021
Procedures
OP-002-003
Operating Procedure Component Cooling Water (Steps 6.4
2
and 6.5)
Procedures
OP-009-002
360
Procedures
OP-903-033
Cold Shutdown IST Valve Tests
Procedures
OP-903-046
Emergency Feed Pump Operability Check
25
Procedures
OP-903-050
Component Cooling Water and Auxiliary Component Cooling
Water Pump and Valve Operability Test
Procedures
OP-903-107
Plant Protection System Channel A B C C Functional Test
318
Procedures
OP-903-115
Train A Integrated Emergency Diesel Generator/Engineering
Safety Features Test
Procedures
OP-903-118
Primary and Auxiliaries Quarterly IST Valve Tests
Procedures
OP-903-121
Safety Systems Quarterly IST Valve Tests
Procedures
OP-904-010
Reactor Trip on Turbine Trip Channel _A _B _C _D
Functional Test
Work Orders
54050174, 53020204, 54084397, 54093512, 54093227,
54091298
Corrective Action
Documents
CR-WF3-YYYY-
NNNN
2016-06698, 2023-01181, 2023-01200, 2023-01208,
23-01232, 2023-01329, 2023-01815
Procedures
OP-901-111
307
Work Orders
2848, 592859