IR 05000202/2030004
| ML24043A127 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, 05000202  |
| Issue date: | 02/13/2024 |
| From: | Bradley Davis Division Reactor Projects II |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2023004 | |
| Download: ML24043A127 (23) | |
Text
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNIT 3 & 4 - INTEGRATED INSPECTION REPORT 05200025/2023004 AND 05200026/2023004
Dear Jamie Coleman:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant (VEGP), Unit 3 & 4 and discussed the results of this inspection with Mr. Patrick Martino, VEGP Units 3 & 4 Site Vice President, 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 II; the Director, Office of Enforcement; and the NRC Resident Inspector at Vogtle Electric Generating Plant, Unit 3 & 4.
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 II; and the NRC Resident Inspector at Vogtle Electric Generating Plant, Unit 3 & 4.
February 13, 2024 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, Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket Nos. 05200025 and 05200026 License Nos. NPF-91 and NPF-92
Enclosure:
As stated
Inspection Report
Docket Numbers:
05200025 and 05200026
License Numbers:
Report Numbers:
05200025/2023004 and 05200026/2023004
Enterprise Identifier:
I-2023-004-0073
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Vogtle Electric Generating Plant, Unit 3 & 4
Location:
Waynesboro, GA
Inspection Dates:
October 01, 2023 to December 31, 2023
Inspectors:
B. Caballero, Senior Operations Engineer
J. Eargle, Senior Resident Inspector
S. Egli, Senior Construction Inspector
C. Even, Senior Reactor Inspector
B. Griman, Resident Inspector
B. Kemker, Senior Resident Inspector
J. Parent, Resident Inspector
J. Walker, Senior Emergency Preparedness Inspector
Approved By:
Bradley J. Davis, Chief
Construction Inspection Branch 2
Division of Construction Oversight
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Vogtle Electric Generating Plant, Unit 3
& 4, 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 to Adequately Implement Containment Closeout Resulting in Loose Debris and Unanalyzed Materials Left in Unit 4 Containment Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05200026/2023004-01 Open/Closed
[H.2] - Field Presence 71111.20 The inspectors identified a finding of very low significance (Green) with an associated NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings for the licensee's failure to properly implement their containment cleanliness and material control closeout procedure prior to and after Unit 4 entering Mode 4.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05200025/2023-006-00 LER 2023-006-00 for Vogtle Electric Generating Plant,
Unit 3 Regarding Automatic Reactor Protection System Actuation During Startup Testing Due to Auto Reactive Power Regulator Being Active While In Island Mode Operation 71153 Closed
PLANT STATUS
Unit 3 Unit 3 was operated at or near 100% rated thermal power during the inspection period.
Unit 4
At the start of this inspection period, Unit 4 was in Mode 3 (Hot Standby) with the licensee investigating the cause for the 2A reactor coolant pump (RCP) trip on September 29.
On October 1, the licensee performed a plant cooldown and the unit entered Mode 4 (Safe Shutdown) to begin a maintenance outage for replacement of the 2A RCP pump motor prior to resumption of plant startup testing activities. The unit entered Mode 5 (Cold Shutdown) on October 3.
On December 23, the licensee completed its final maintenance outage activities and required testing, established conditions to begin plant heat up, and the unit entered Mode 4 (Safe Shutdown). On December 25, the licensee completed additional required testing and continued plant heat up for the unit to enter Mode 3 (Hot Standby). On December 30, the licensee performed a plant cooldown to Mode 4 (Safe Shutdown) and subsequently to Mode 5 (Cold Shutdown) on December 31 to address abnormal vibrations on trains B and D of ADS stage 4 piping.
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)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal winter temperatures.
- (1) Passive Containment Cooling System during the weeks of November 26 and December 10, 2023.
71111.04 - Equipment Alignment
Partial Walkdown Sample [AP1000] (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 3 passive containment cooling system during the week of October 29, 2023.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample [AP1000] (IP Section 03.01) (2 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) Unit 3 Diesel Generator Building on October 19, 2023.
- (2) Unit 4 PXS B and RNS Valve Room on October 26, 2023.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protection in the Unit 4 Auxiliary Building Elevation 66'6" on October 4, 2023.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations and biennial written examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates following the administration of the requalification annual operating tests and the biennial written examinations administered, which the facility licensee completed on 9/27/23 and 9/28/23, respectively.
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 Main Control Room during performance of 4-GOP-102, "Draining the Reactor Coolant System (RCS)" on October 5, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification training in the simulator on October 31, 2023.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample [AP1000] (IP Section 03.01) (2 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) Unit 4 risk mitigation activities with the RCS at reduced inventory during the week of October 15, 2023.
- (2) Unit 3 online risk management of planned and emergent work activities during the week of November 26, 2023.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment [AP1000] (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) ODS-CR-11009833, Backleakage from RCS into CVS Makeup Line (2)
===11017912-Unit 3-ODS, Potential Use of Plywood in Unit 3 Containment Elevator Construction
- (3) TE 1138793, Past Operability Review - Plywood in Unit 4 Containment Elevator
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01)===
- (1) The inspectors evaluated the Unit 4 outage activities including the 2A reactor coolant pump replacement and the ADS stage 4 vibration issues from October 1 through December 31, 2023.
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) [AP1000] (IP Section 03.01) (2 Samples)
- (1) Work Order # SNC1599740, Re-install 4-RCS-PL-L095 to Support 4-RCS-MP-02A Restoration on November 20, 2023.
- (2) PCI Weld Process Traveler # 920484-005, Unit 4 / Pipe Support RCS-PH-11R2189 Reinstall on November 29, 2023.
Surveillance Testing [AP1000] (IP Section 03.01) (1 Sample)
(1)3-RLS-CSP-001, Hot Leg Grab Sample from RCS Train A on October 30, 2023.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency Preparedness Training Evolution on November 1, 2023.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Emergency Preparedness Drill on October 10,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (DEP) Sample [AP1000] (IP Section 02.12)===
- (1) April 1, 2023 through December 31, 2023 EP02: Emergency Response Organization (ERO) Drill Participation [AP1000] (IP Section 02.13) (1 Sample)
- (1) April 1, 2023 through December 31, 2023 EP03: Alert And Notification System (ANS) Reliability Sample [AP1000] (IP Section 02.14) (1 Sample)
- (1) April 1, 2023 through December 31, 2023 BI01: Reactor Coolant System (RCS) Specific Activity Sample [AP1000] (IP Section 02.10) (1 Sample)
- (1) Unit 3 (March 13, 2023 through September 25, 2023)
BI02: RCS Leak Rate Sample [AP1000] (IP Section 02.11) (1 Sample)
- (1) Unit 3 (December 16, 2022 through October 30, 2023)
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) CAR 80000109, ADS Stage 4 Actuation Received during Maintenance Activity
- (2) CAR 507319, Foreign Material in Core Makeup Line
- (3) CAR 430119, Work Hour Rule Implementation Review
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
The inspectors reviewed the licensees corrective action program and other licensee trending programs for potential adverse trends in its corrective action program (CAP) that might be indicative of a more significant safety issue.
- (1) Assessment and Observations The inspectors determined the licensee's trending program was generally effective at identifying, monitoring, and correcting adverse performance trends before they could become more significant safety problems. The inspectors' evaluation did not reveal any new trends that would indicate a more significant safety issue. The inspectors determined, in most cases, issues were appropriately evaluated by the licensee's staff for potential trends at a low threshold and resolved within the scope of the CAP.
The inspectors observed a trend associated with an increase in CRs for personnel qualification standards (PQ&S) / fatigue/work hour waivers. The inspectors noted there were multiple CRs emphasizing the amount of fatigue/work hour waivers being processed. The inspectors also noted a trend with Level 2 CRs not being closed within 9 days in accordance with procedure ND-AD-002-028, Corrective Action Program Instructions.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report [AP1000] (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05200025/2023-006-00, "Automatic Reactor Protection System Actuation During Startup Testing Due to the Auto Reactive Power Regulator Being Active While in Island Mode Operation." (ADAMS Accession No. ML23262A958)
The inspectors determined the cause of the condition described in the LER was not reasonably within the licensee's ability to have foreseen and corrected and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. This LER is closed.
INSPECTION RESULTS
Failure to Adequately Implement Containment Closeout Resulting in Loose Debris and Unanalyzed Materials Left in Unit 4 Containment Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05200026/2023004-01 Open/Closed
[H.2] - Field Presence 71111.20 The inspectors identified a finding of very low significance (Green) with an associated NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings for the licensee's failure to properly implement their containment cleanliness and material control closeout procedure prior to and after Unit 4 entering Mode 4.
Description:
After the licensee had completed containment cleanliness activities in accordance with procedure 4-CNS-SOP-001 Attachment 4, Containment Closeout Inspection, the inspectors identified loose debris and materials that were not allowed to be inside containment during operation without an evaluation by the licensee in accordance with its procedure. The primary purpose of this procedure was to ensure no loose debris/materials were left in containment prior to plant start up from an outage that could either contribute to recirculation sump screen blockage during a design basis accident or get transported into a direct vessel injection or a cold leg LOCA break that becomes submerged during a design basis accident.
On September 20, the inspectors completed their independent verification of containment cleanliness prior to the licensee entering Mode 4. The inspectors identified fibrous and latent debris consisting of items such as lanyards, pig matting, wire brushes, metal clamps, tubing, paper, cords, plastic bottles, tape, and tie wraps. After identification of the material by the inspectors, the licensee removed these items from containment prior to entering Mode 4 on September 21, and Mode 3 on September 25, during which time the containment debris limits affecting operability of safety systems became applicable. The licensee documented the issue in their corrective action program as CRs 11009227 and 11014122.
On October 1, the licensee transitioned the plant to Mode 4, and then transitioned the plant to Mode 5 on October 3. On October 10, the NRC inspectors entered containment and identified a 4ft x 6ft sheet of plywood in the containment elevator shaft. This sheet of plywood exceeded the design limits of 6.6lbs of fibrous material. The licensee entered this issue in their corrective action program as CR 11014112, and performed a past operability review because the fibrous material was inside containment while the plant was in Mode 4. Based on the location of the material being outside of the recirculation flowpath and the fact that the plant had never achieved initial criticality to produce latent heat, the licensee concluded that the plywood would not have affected the operability of the core heat removal function during a design basis accident. The plywood was removed from containment prior to the plant transitioning to Mode 4 on December 23.
Corrective Actions: The licensee entered this violation into its CAP as CRs 11009227, 11014122, and 11014112 to evaluate the cause and to identify appropriate corrective actions.
The licensee took immediate corrective actions to remove the debris found by the inspectors and evaluated the past operability of the core heat removal function during a design basis accident.
Corrective Action References: CR 11009227, Debris Found During NRC Mode 4 Inspection, 09/22/2023 CR 11014122, GSI-191 Containment Cleanliness Debris Limits Exceeded, 10/10/2023 CR 11014112, 4' X 6' Sheet Of Plywood Found In U4 Containment Elevator Shaft, 10/10/2023
Performance Assessment:
Performance Deficiency: The licensees failure to perform an adequate containment cleanliness and material control closeout prior to and after Unit 4 entering Mode 4 in accordance with procedure 4-CNS-SOP-0 was a performance deficiency.
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. 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, loose materials/debris in containment could result in the materials/debris being transported to the recirculation sump screens in the event of design basis accident and adversely affect the sump performance or get transported into a direct vessel injection or a cold leg LOCA break that becomes submerged during a design basis accident and collect in reactor core flow channels.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix G, Shutdown Safety SDP. The inspectors assessed the significance of the finding using IMC 0609 Appendix G, Shutdown Operations Significance Determination Process. The inspectors performed a Phase 1 SDP review of this finding using IMC 0609, Appendix G, Attachment 1, "Shutdown Operations Significance Determination Process Phase 1 Initial Screening and Characterization of Findings, and determined this finding was of very low safety significance (Green) based on No answers to all of the Exhibit 3 - Mitigating Systems Screening Questions.
Cross-Cutting Aspect: H.2 - Field Presence: Leaders are commonly seen in the work areas of the plant observing, coaching, and reinforcing standards and expectations. Deviations from standards and expectations are corrected promptly. Senior managers ensure supervisory and management oversight of work activities, including contractors and supplemental personnel.
H.2 - Field Presence: Leaders are commonly seen in the work areas of the plant observing, coaching, and reinforcing standards and expectations. Deviations from standards and expectations are corrected promptly. Senior managers ensure supervisory and management oversight of work activities, including contractors and supplemental personnel.
The inspectors determined the finding had a cross-cutting aspect of Field Presence in the Human Performance area because the licensee failed to ensure adequate supervisory and management oversight of the containment closeout process was conducted to ensure proper performance of containment cleanliness and material control closeout procedures prior to and after Unit 4 entered Mode 4.
Enforcement:
Violation: 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings states, in part, that 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.
3-CNS-SOP-001, Attachment 4, Step 4.5.a states: Locally check loose debris is NOT present in accessible areas of containment. IF loose debris is present in containment, THEN perform one of the following:
- Remove debris OR
- Document presence of debris per B-GEN-ENG-032-002, Control of Unattended Temporary Material in Containment in Modes 1-4.
Contrary to the above, from September 20, 2023, through October 10, 2023, NRC inspectors identified loose materials/debris, including fibrous materials, present in the Unit 4 containment without it having been documented or evaluated as acceptable to remain in containment in Modes 1 - 4.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 23, 2024, the inspectors presented the integrated inspection results to Mr.
Patrick Martino, VEGP 3&4 Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
3-PCS-SOP-001
Passive Containment Cooling System
Version 3.0
Procedures
4-PCS-SOP-001
Passive Containment Cooling System
Version 1.0
Procedures
B-GEN-OPS-009
Cold Weather Checklist
Version 4.0
Procedures
NMP-OS-017
Severe Weather
Version 3.1
Drawings
APP-PCS-M6-
001
Piping and Instrumentation Diagram Passive Containment
Cooling System
Revision 12
Drawings
APP-PCS-M6-
2
Piping and Instrumentation Diagram Passive Containment
Cooling System
Revision 14
Drawings
APP-PCS-M6-
003
Piping and Instrumentation Diagram Passive Containment
Cooling System
Revision 10
Drawings
APP-PCS-M6-
004
Piping and Instrumentation Diagram Passive Containment
Cooling System
Revision 10
Procedures
3-PCS-SOP-001
Passive Containment Cooling System
Version 3.0
Corrective Action
Documents
Resulting from
Inspection
CR 11016977
NRC Identified Housekeeping Issues in Unit 3 Diesel
Building A & B
Fire Plans
B-PFP-ENG-001-
F3101
Pre-Fire Plan - Containment Building EL 82'-6"
Version 2.0
Fire Plans
B-PFP-ENG-001-
F3102
Pre-Fire Plan - Containment Building EL 92'-6"
Version 2.0
Fire Plans
B-PFP-ENG-001-
F3600
Pre-Fire Plan - Diesel Generator Building
Version 4.0
Corrective Action
Documents
CR 10977535
Corrective Action
Documents
CR 50178817
Miscellaneous
Vogtle 3&4 QA Monthly Report
August 2023
Miscellaneous
Procedures
4-AOP-908
Internal Flooding Response
1.0
Procedures
4-AOP-908-B
Background document for 4-AOP-908 Internal Flooding
Response
1.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
4-GOP-102
Draining the Reactor Coolant System (RCS)
Version 3.0
Corrective Action
Documents
CR 11015501
Unexpected alarm on A Diesel Generator.
10/15/2023
Miscellaneous
Work Logs Review
10/15/2023
Procedures
B-ADM-OPS-018
Protected Division and Protected Equipment Program
Version 3.0
Procedures
B-ADM-OPS-018
Protected Division and Protected Equipment Program
Version 3.0
Procedures
NMP-DP-001
Operational Risk Awareness
Version 24.3
Procedures
NMP-GM-031
On-Line Configuration Risk Management Program
Version 9.4
Procedures
NMP-GM-031-
001
Online Maintenance Rule (a)(4) Risk Calculations
Version 8.0
Corrective Action
Documents
CR 11014112
4' x 6' 3/4" Sheet Of Plywood Found In U4 Containment
Elevator Shaft
10/20/2023
Corrective Action
Documents
CR 11009833
Back-leakage from RCS into CVS Makeup lines
09/25/2023
Corrective Action
Documents
CR 11014122
GSI-191 Containment Cleanliness Limits Exceeded
10/11/2023
Corrective Action
Documents
CR 11017912
Potential Use of Plywood in U3 Containment Elevator
Construction
10/23/2023
Corrective Action
Documents
TE 1138793
Past Operability Review - Plywood in U4 Containment
Elevator
10/12/2023
Miscellaneous
3.0
Miscellaneous
Vogtle Units 3
and 4 Technical
Specifications
and Basis
Technical specification 5.5.3 Inservice Testing Program
Operability
Evaluations
11009833-U4-
ODS
Back-leakage from RCS into CVS Makeup lines
09/28/2023
Operability
Evaluations
11017912-Unit3-
ODS
Potential Use of Plywood in U3 Containment Elevator
Construction
11/20/2023
Procedures
4-CVS-OTS-10-
2
Chemical And Volume Control System Check Valve
Exercise Test
1.0
Procedures
NMP-AD-012
16.1
Procedures
NMP-AD-012-F01
Operability Determination Support bases
4.1
Corrective Action
11007847
Permanent ADS 4 Sensors Out Of Line
09/18/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
11017846
Unit 4 entry into TR 3.0.3 due to RCP 2A Replacement
Outage
10/23/2023
Corrective Action
Documents
CR 11025404
Base Metal Repairs required for Electrical Supports in 11202
(Support RCP 2A replacement)
11/17/2023
Corrective Action
Documents
CR 11025415
Base Metal Repair for 1120-1251618-C15-028 (Supports
RCP 2A Replacement)
11/17/2023
Corrective Action
Documents
CR 11033385
Unit 4 ADS 4 Vibration Alarm in
2/21/2023
Corrective Action
Documents
CR 11034094
High Vibrations on Stage 4 ADS B & D
2/26/2023
Corrective Action
Documents
Resulting from
Inspection
CR 11008843
T&B "Ty-Rap and 3M Co. No. 35 Insulating/Color Coding
Tapes
09/21/2023
Corrective Action
Documents
Resulting from
Inspection
CR 11009227
Debris Found During NRC Mode 4 Inspection
09/22/2023
Corrective Action
Documents
Resulting from
Inspection
CR 11014112
4' X 6' Sheet Of Plywood Found In U4 Containment Elevator
Shaft
10/10/2023
Corrective Action
Documents
Resulting from
Inspection
CR 11014122
GSI-191 Containment Cleanliness Debris Limits Exceeded
10/10/2023
Engineering
Changes
SNC1643809
Impact damage to RCP 2A and 2B Flanges During
Installation
Rev. 0
Engineering
Evaluations
1141432
Base Metal Repair for 1120-1251618-C15028 (Supports
RCP 2A Replacement)
11/18/2023
Miscellaneous
APP-GW-GLR-
079
AP1000 Verification of Water Sources for Long-Term
Recirculation Cooling Following a LOCA
Rev. 9
Miscellaneous
APP-MH17-VNM-
AP1000 RCP Installation Cart Technical Manual
Rev. 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
001
Miscellaneous
SV4-MP01-MEW-
1016971
ASME III - Install RCP 2A Heat Exchanger SV4-RCS-MP-
2A_HX Including Associated Piping
Rev. 0
Operability
Evaluations
TE 1138793
Past Operability Review - Plywood in U4 Containment
Elevator
10/12/2023
Procedures
4-CNS-SOP-001
Containment System, Attachment 4, Containment Closeout
Inspection
Version 2.0
Procedures
4-GEN-ITPS-606
Post-Fuel Loading Precritical Test Sequence Startup Test
Procedure
Version 2.0
Procedures
4-GEN-ITPS-618
Power Ascension Test Sequence Startup Test Procedure
Version 3.0
Procedures
4-GOP-205
Plant Cooldown Mode 3 to Mode 5
Version 1.0
Procedures
4-GOP-301
Mode Change Checklists
Version 1.1
Procedures
4-GOP-303
Plant Heatup Mode 5 to Normal Operating Temperature
Version 3.0
Procedures
4-RNS-SOP-001
Normal Residual Heat Removal System
Version
E=0.4
Procedures
B-GEN-ENG-032
Containment Cleanliness and Sampling Program
Version 1.0
Procedures
B-GEN-ENG-032-
001
Containment Debris Sampling
Version
A=0.0
Procedures
B-GEN-ENG-032-
2
Control of Temporary Unattended Material in Containment in
Modes 1-4
Version 1.1
Procedures
B-GEN-OPS-006
Containment Entry
Version 3.1
Work Orders
SNC1588324
RCP 2A - Reinstall RCP Heat Exchanger
Rev. 0
Work Orders
SNC1599802
Assemble / Disassemble / Reconfigure RCP Installation Cart
For 4-RCS-MP-02A Replacement
Rev. 0
Work Orders
SNC1607533
Perform post work testing on ADS stage 4 vib sensors 4-
RCS-YE341D (ADS Stage 4 V014D X Vib).
Rev. 0
Miscellaneous
PCI Traveler
Number 920484-
005
Unit 4 / Pipe Support RCS-PH-11R2189 Reinstall
Procedures
3-RLS-CSP-001
Primary System Sampling Using the RSI Primary Sampling
Panel
Version 5.0
Procedures
B-GEN-CRC-002
Guidelines for Radiochemistry Data Review Using APEX
Version 1.0
Work Orders
SNC1599740
Re-install 4-RCS-PL-L095 to support 4-RCS-MP-02A
Restoration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 11014269
VEGP 3&4 ERO Training Drill (Simulator EDS Issues)
10/11/2023
Corrective Action
Documents
CR 11014278
VEGP 3&4 ERO Training Drill (TSC EPBX Phone Plant
Page Issue)
10/11/2023
Miscellaneous
Drill Packet for the October 10, 2023 Emergency
Preparedness Drill.
10/10/2023
Miscellaneous
AP-LT-C-SG-
241B
LOCT 24-1 Integrated Training Scenario 241B
Revision 1.2
Procedures
NMP-EP-146-F01
CR Emergency Director
Revision 6
Procedures
NMP-EP-303-F02
Drill and Exercise Comment and Feedback Form
2.0
Procedures
NMP-EP-303-F03
Drill & Exercise Observation Form
1.0
71151
Miscellaneous
eSOMS Narrative / Unit Logs
71151
Procedures
SNC Standard Emergency Plan
Rev. 7
71151
Procedures
3-RLS-CSP-001
Primary System Sampling Using the RSI Primary Sampling
Panel
Version 5.0
71151
Procedures
B-GEN-CRC-002
Guidelines for Radiochemistry Data Review Using APEX
Version 1.0
71151
Procedures
NMP-AD-029
Preparation and Reporting of Regulatory Assessment
Performance Indicator Data and the Monthly Operating
Report
Rev. 3.2
71151
Procedures
NMP-EP-308
SNC Emergency Alert Siren Operation, Testing and
Maintenance
Rev. 4.1
Corrective Action
Documents
Foreign Material Found in Core Makeup
Corrective Action
Documents
ATV-CAR-80008714 Perform O&P IAW ND-AD-006
Requirement ADS Stage 4 Actuation Received during
Maintenance Activity
Corrective Action
Documents
CR 1090022
April PQS review
05/08/2023
Corrective Action
Documents
CR 10957063
Work hour waiver
03/16/2023
Corrective Action
Documents
CR 10957305
Work hour waiver
03/17/2023
Corrective Action
Documents
CR 10957416
Work hour waiver
03/18/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 10957543
Work hour waiver
03/18/2023
Corrective Action
Documents
CR 10961421
Work hour waiver
03/31/2023
Corrective Action
Documents
CR 10961650
Work hour waiver
04/02/2023
Corrective Action
Documents
CR 10961747
Work hour waiver
04/03/2023
Corrective Action
Documents
CR 10961863
Work hour waiver
04/03/2023
Corrective Action
Documents
CR 10962231
Work hour waiver
04/04/2023
Corrective Action
Documents
CR 10962272
Work hour waiver
04/04/2023
Corrective Action
Documents
CR 10962577
Work hour waiver
04/05/2023
Corrective Action
Documents
CR 10962869
Work hour waiver
04/06/2023
Corrective Action
Documents
CR 10963509
Work hour waiver
06/27/2023
Corrective Action
Documents
CR 10963719
Work hour waiver
04/11/2023
Corrective Action
Documents
CR 10964151
Work hour waiver
04/12/2023
Corrective Action
Documents
CR 10964165
Work hour waiver
04/12/2023
Corrective Action
Documents
CR 10965908
Work hour waiver
04/12/2023
Corrective Action
Documents
CR 10966124
Work hour waiver
04/20/2023
Corrective Action
Documents
CR 10966251
Work hour waiver
04/21/2023
Corrective Action
Documents
CR 10966278
Work hour waiver
04/21/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 10967156
Work hour waiver
04/26/2023
Corrective Action
Documents
CR 10967892
Work hour waiver
04/28/2023
Corrective Action
Documents
CR 10968034
Work hour waiver
04/30/2023
Corrective Action
Documents
CR 10968844
Work hour waiver
05/03/2023
Corrective Action
Documents
CR 10969257
Work hour waiver
05/04/2023
Corrective Action
Documents
CR 1096941
Work hour waiver
05/03/2023
Corrective Action
Documents
CR 10969412
Work hour waiver
05/05/2023
Corrective Action
Documents
CR 10969763
Work hour waiver
05/07/2023
Corrective Action
Documents
CR 10969952
Work hour waiver
05/08/2023
Corrective Action
Documents
CR 10970939
Work hour waiver
05/11/2023
Corrective Action
Documents
CR 10971265
April PQS validations
05/12/2023
Corrective Action
Documents
CR 10977804
Late validations
06/07/2023
Corrective Action
Documents
CR 10978349
Operations PQS validations
06/08/2023
Corrective Action
Documents
CR 10979104
May PQS review
06/12/2023
Corrective Action
Documents
CR 10981610
Ops schedule change not updated in PQS
06/20/2023
Corrective Action
Documents
CR 10982070
PQS timeliness
06/22/2023
Corrective Action
Documents
CR 10983575
Discrepancy between time worked and PQS
06/27/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 10983737
Identified work hour waiver deficiencies
06/28/2023
Corrective Action
Documents
CR 10983899
Work performed without PQS being updated
06/28/2023
Corrective Action
Documents
CR 10985348
Late PQS validation
07/05/2023
Corrective Action
Documents
CR 10985348
PQS not updated before work occurred
07/05/2023
Corrective Action
Documents
CR 10985724
PQS not updated before work occurred
07/06/2023
Corrective Action
Documents
CR 10985959
June PQS review
07/07/2023
Corrective Action
Documents
CR 1098601
Potential work hour violation not flagged by PQS
07/10/2023
Corrective Action
Documents
CR 10986620
PQS not configured to calculate min day off during outage
07/10/2023
Corrective Action
Documents
CR 10986632
Fatigue assessment
07/10/2023
Corrective Action
Documents
CR 10987476
Mid-year Part 26 review
07/13/2023
Corrective Action
Documents
CR 10987655
Work hour rule violation not recognized
07/13/2023
Corrective Action
Documents
CR 10987664
June PQS revalidations
07/13/2023
Corrective Action
Documents
CR 10987751
Unrecognized work hour rule violation
07/13/2023
Corrective Action
Documents
CR 10987845
Work hour rule not recognized
07/14/2023
Corrective Action
Documents
CR 50179773
ADS Stage 4 Actuation Received during Maintenance
Activity
Corrective Action
Documents
CR 90000368
CR 50179773 ADS Stage 4 Actuation during Maintenance
Activity
Corrective Action
Documents
TE 1137826
Ensure CIM Audit Was Performed Nightly until Configuration
Control Was Established
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
TE 1137828
Ensure 7 Risk-Based Questions Are Being Asked at Work
Controls by Each WCC SRO or Every Work Group
Corrective Action
Documents
TE 1138943
Ensure Proper Oversight for All Vendors
Miscellaneous
60-Day Optional 10 CFR 50.73(a)(1) Report of Invalid
Specified System Actuation
Corrective Action
Documents
PQ&S Waivers/Violations Adverse Trend
Corrective Action
Documents
Perform CCA for Adverse Trend in Unit 3 CAP CRs not
closed within 9 Days
Corrective Action
Documents
CR 10967156
PQ&S Waivers/Violations Adverse Trend
Corrective Action
Documents
CR 11010437
Adverse Trend in Unit 3 CAP CRs Not Closed Within 9 Days
- MRC Identified
Corrective Action
Documents
CR 11017115
NDQA Identified - Basis For Fatigue Management Waiver
Did Not Meet Procedure Requirements
Corrective Action
Documents
CR 11017120
NDQA Identified - Fatigue Management Waiver Form -
Section 3 Was Incomplete Per Procedure Requirements
Corrective Action
Documents
CR 11017146
WEC CAP IR 2023-6889 - Communication Of Westinghouse
CAP Items (SVP_SV0_230248) PIN 02822
Corrective Action
Documents
CR 11018220
Weekly Review of PQ&S Data 9/3-9/9/2023 - Operations
Corrective Action
Documents
TE 1129429
Add Work Hour Rule Software Training To SRO Continuing
Training (SRO LOCT)
Corrective Action
Documents
TE 1129430
Scheduling: Complete Business Case To Evaluate Better
Software To Track Work Hour Rules And Schedule
Corrective Action
Documents
TE 1129663
Raise Licensed and Non-licensed Operations Staffing
Corrective Action
Documents
TE 1140428
Evaluate CR Closure Timeliness
Miscellaneous
Unit 3 & 4 Weekly Management Review Committee Packet
Miscellaneous
Audit Report #
23-S&W-2
ASME QAI-1 Audit
07/24/2023
Procedures
NMP-GM-003
Self-Assessment and Benchmark Procedure
Version 35.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Unplanned Reactor Trip During 3-GEN-ITPS-633, 100%
Load Rejection Startup Test Procedure
Engineering
Changes
E&DCR SV3-
ZAS-GEF-034
MSU Relay RY1 V/Hz Trip
Revision 0
Engineering
Changes
SNC 1520848
Change to PLS Logic to Disable AQR Mode When Plant
Enters Island Mode
Revision 0
Miscellaneous
LER 2023-006-00
Automatic Reactor Protection System Actuation During
Startup Testing Due to the Auto Reactive Power Regulator
Being Active While in Island Mode Operation
09/19/2023
Procedures
3-GEN-ITPS-633
100% Load Rejection Startup Test Procedure
Version 5.0
Procedures
3-GOP-101
Power Operations Above 25% Power
Version 2.0