IR 05000458/2025001
| ML25119A328 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/06/2025 |
| From: | Douglas Dodson NRC/RGN-IV/DORS/PBC |
| To: | Hansett P Entergy Operations |
| Dodson D | |
| References | |
| IR 2025001 | |
| Download: ML25119A328 (1) | |
Text
May 06, 2025
SUBJECT:
RIVER BEND STATION - INTEGRATED INSPECTION REPORT 05000458/2025001
Dear Phil Hansett:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at River Bend Station. On April 10, 2025, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation that was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation 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 River Bend Station. 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, Douglas E. Dodson II, Chief Reactor Projects Branch C Division of Operating Reactor Safety Docket No. 05000458 License No. NPF-47
Enclosure:
As stated
Inspection Report
Docket Number:
05000458
License Number:
Report Number:
Enterprise Identifier:
I-2025-001-0006
Licensee:
Entergy Operations, Inc.
Facility:
River Bend Station
Location:
St. Francisville, LA
Inspection Dates:
January 1, 2025, to March 31, 2025
Inspectors:
B. Baca, Health Physicist
J. Mejia, Reactor Inspector
J. O'Donnell, Senior Health Physicist
E. Powell, Resident Inspector
C. Wynar, Senior Resident Inspector
Approved By:
Douglas E. Dodson, II, Chief
Reactor Projects Branch C
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at River Bend Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified non-cited violation is documented in report section: 71111.08G.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
River Bend Station began the inspection period at 100 percent rated thermal power. On January 24, 2025, the station reduced power to approximately 82 percent for a planned control rod pattern adjustment. On January 25, 2025, power was restored to 100 percent. Power remained at 100 percent until February 11, 2025, when the licensee shut down the plant by placing the mode switch in shut down for a planned refueling and maintenance outage. The plant remained shut down and at 0 percent power until March 30, 2025, when the mode switch was taken to startup. The station ended the inspection period in the middle of the startup procedure at approximately 3 percent rated thermal power.
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 onsite 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 subfreezing temperatures and snow for the following systems:
- instrument air system; service air system; condensate storage, makeup and transfer system; and makeup water system on January 22, 2025
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the stations overall preparations to protect risk-significant systems from impending severe thunderstorms and during a tornado watch on March 14, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)high pressure core spray system on March 13, 2025 (2)low pressure core spray system on March 13, 2025 (3)reactor core isolation cooling system on March 31, 2025 (4)low pressure coolant injection B system on March 31, 2025
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)hydraulic control unit area west, fire area RC-4/Z-3, on February 25, 2025 (2)shield building access area, fire area AB-15/Z-2, on March 6, 2025 (3)annulus, fire area RC-6, on March 12, 2025 (4)recirculation pump area, fire area RDW-1, on March 19, 2025 (5)fuel storage pool area, fire area FB-1/Z-1, on March 28, 2025
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire brigade drill on January 15, 2025.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) spent fuel pool cooling heat exchanger SFC-E1A on March 31, 2025
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
The inspectors evaluated boiling water reactor nondestructive testing by reviewing the following activities in Unit 1 during refueling outage 23 from February 17 to March 13, 2025:
(1)
Ultrasonic Examinations i.
low pressure core spray, CSH-027A-FW001, valve to pipe ii.
high pressure core spray, CSL-042A-FW002, pipe to valve iii.
reactor pressure vessel, B13-D001-N07-1, nozzle to vessel iv.
reactor pressure vessel, B13-D001-N07-0, nozzle inner radius v.
reactor pressure vessel, B13-D001-N08-1, nozzle to vessel vi.
reactor pressure vessel, B13-D001-N08-0, nozzle inner radius vii.
reactor pressure vessel, B13-D001-S-1-64, studs 1-64 b.
Penetrant Dye Examinations i.
standby liquid control, SLS-037D-FW002, elbow to pipe ii.
standby liquid control, SLS-037D-FW003A, pipe to elbow iii.
standby liquid control, SLS-037D-FW004, elbow to pipe c.
Visual Examinations i.
main steam, MSS-PSA-3046-A1, pipe support-anchor ii.
main steam, MSS-PSSH-3044-A1, pipe support-spring iii.
reactor pressure vessel, B13-D001-NT-1-64, nuts 1-64 iv.
reactor pressure vessel, B13-D001-WA-1-64, washers 1-64 v.
containment, DS-001, dome section vi.
containment, DS-003, dome section vii.
containment, WS-04, inside wall section viii.
containment, WS-07, inside wall section ix.
containment, WS-13, inside wall section
- There were no relevant indications accepted for continued service.
- Welding Activities a.
work order (WO) 54243150-01, -03, mechanical piping, RCS-750-119, FW-006AF, FW-015F, SW-013F, SW-014F b.
WO 589506-50, nozzle, G36-RYV081A, XI-FW002A
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 shutdown for refueling outage 23 on February 10, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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)elevated risk during unplanned 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limiting condition for operation on January 28, 2025 (2)elevated risk during division 3 battery discharge test on January 31, 2025 (3)elevated risk during standby service water A nozzle inspection on February 6, 2025 (4)elevated risk during division 1 shutdown protected equipment and residual heat removal A shutdown cooling on February 11, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)control building chiller A trip on January 13, 2025 (condition report (CR)-RBS-2025-
===00140) (2)jet pump 6 damage/repair on March 18, 2025 (CR-RBS-2025-01075)
(3)service water return header B isolation valve (SWP-MOV96B) failed to fully close on March 25, 2025 (CR-RBS-2025-00585)
(4)emergency diesel generator surveillance 3.8.1.18 and 3.8.1.11 on March 28, 2025 (CR-RBS-2025-01409)
(5)leaking main steam isolation valve on March 31, 2025 (CR-RBS-2025-00802, CR-RBS-2025-00818, and CR-RBS-2025-00819)
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated Refueling Outage 23 activities from February 11, 2025, to March 31, 2025. The inspectors completed inspection procedure Sections 03.01.a, 03.01.b, and 03.01.c.
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) WO 54020454, main steam isolation valve operability testing, on March 2, 2025
- (2) WO 54249451, standby liquid control system Amphenol cable replacement, on March 4, 2025
- (3) WO 00551736, reactor core isolation cooling trip throttle repair, on March 13, 2025
- (4) WO 54250336, jet pump 6 repair, on March 14, 2025
- (5) WO 00555639, control building chiller A controller repair for hot gas bypass valve, on March 31, 2025
- (6) WO 54089055, low pressure core spray minimum flow check valve CSL-V10 repair, on March 31, 2025
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) STP-508-4244, RPS/EOC-RPT Turbine First Stage Pressure Channel Calibration and Logic System Functional Test, Revision 015 on March 4, 2025
- (2) STP-107-3806, Feedwater Penetration KJB-Z3A Valve Leak Rate Test, Revision 018 on March 12, 2025
- (3) STP-309-0601, Division I ECCS Test, Revision 059 on March 18, 2025
- (4) STP-051-4269, ATWS/Recirc Pump Trip Reactor Vessel Pressure High Channel Calibration and Logic System Functional Test, Revision 302 on March 31, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) STP-204-6303, Div I RHR Quarterly Valve Operability Test, Revision 22 on March 12, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) WO 00596880, main steam isolation valve B21-AOVF022B, on March 25,
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)surveys of potentially contaminated material leaving the radiologically controlled area (RCA)
(2)workers exiting the RCA at the T Tunnel 95' RCA exit during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)work under vessel installing local range power monitors using radiation work permit (RWP) 2025-1917 (2)removal of safety relief valve B21-RVF041D using RWP 2025-1912 (3)dry run of control rod drive mechanism removal under vessel using RWP 2025-1917 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):
(1)
(VHRA) reactor building 131' - inclined fuel transfer system (IFTS) blind flange area gate (2)
(VHRA) fuel building 131' - mid support room gate (3)
(HRA) auxiliary building 141' - main steam tunnel (floor plugs removed)
(4)
(HRA) auxiliary building 95' - reactor water cleanup pump room door (5)
(HRA) radwaste building 90' - six-way valve room 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.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
(1)control room fresh air system (2)technical support center engineered safety feature ventilation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)refuel floor reactor vessel stud washer cleaning station with high efficiency particulate air (HEPA) filtration
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
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 through December 31, 2024 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) January 1 through December 31, 2024
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) January 1 through December 31, 2024
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) January 1 through December 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) January 1 through December 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)division 3 battery room temperature (2)high main steam tunnel temperatures resulting from incorrect fan blade pitch on main steam tunnel unit cooler HVR-UC8 (3)reactor core isolation cooling single failure criteria
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.08G This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records, requires that sufficient records shall be maintained to furnish evidence of activities affecting quality.
The records, in part, shall include the results of the inspections. Records shall be identifiable and retrievable.
Contrary to the above, from March 21, 2023, to February 18, 2025, the licensee failed to maintain records to furnish evidence of activities affecting quality, in that, results of an inspection were not maintained in records that were identifiable and retrievable. Specifically, the licensee discovered a copy of a field pressure test visual examination report with unidentifiable results in the observed conditions section that was signed by the examiner.
Another copy of the report was found in the database with the observed conditions but was not signed by the examiner and unable to be signed by the examiner after discovery. The original field report was not found. The report was from refueling outage 22, dated March 21, 2023, and was not processed within the 30-day requirement of licensee procedure EN-AD-103, Document Control and Records Management Program, Revision 28.
Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At Power. The inspectors screened the finding using Table 2 of IMC 0609, Attachment 4, Initial Characterization of Findings. The Barrier Integrity Cornerstone Note directs all other reactor coolant system boundary issues to be considered under the Initiating Events Cornerstone.
IMC 0609, Attachment 4, Table 3, routes the finding to the IMC 0609, Appendix A, Exhibit 1, Loss of Coolant Accident (LOCA) Initiators questions. Since the finding:
- (1) could not result in exceeding the reactor coolant system leak rate for a small LOCA and
- (2) could not have likely affected other systems used to mitigate a LOCA, the finding screens as Green. The finding represents the potential of missed exams and records within the pressure test program.
Corrective Action References: CR-RBS-2025-01712
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On February 25, 2025, the inspectors presented the occupational radiation safety inspection results to Brad Wertz, General Manager of Plant Operations, and other members of the licensee staff.
- On March 13, 2025, the inspectors presented the inservice inspection activities results to Phil Hansett, Site Vice President, and other members of the licensee staff.
- On April 10, 2025, the inspectors presented the integrated inspection results to Phil Hansett, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Severe Weather Operation
Procedures
SOP-0031
Residual Heat Removal SYS 204
348
Procedures
SOP-0035
Reactor Core Isolation Cooling System (SYS #209)
R-STM-0203
Miscellaneous
R-STM-0205
Low Pressure Core Spray
Calculations
G13.18.12.2-022
River Bend Station - Combustible Loading
010
Procedures
ADM-0073
Temporary Services and Equipment
309
Procedures
Control of Combustibles
Procedures
RB-095-001
Recirculation Pump Area Fire Area RDW-1
Procedures
RB-114-005
HCU Area West RC-4/Z-3
Corrective Action
Documents
CR-RBS-
2012-03147, 2012-03680, 2023-01603, 2023-01815, 2023-
01830, 2023-02153, 2023-02706, 2023-03001, 2023-03300,
23-03414, 2023-03584, 2023-04243, 2023-04246, 2023-
247, 2023-04618, 2023-06236, 2024-00646, 2024-00646,
24-00677, 2024-03183, 2024-05802, 2024-05803, 2025-
00650, 2025-00714, 2025-00808, 2025-00938, 2025-00970,
25-01015, 2025-01018, 2025-01019, 2025-01021, 2025-
01052
Corrective Action
Documents
Resulting from
Inspection
CR-RBS-
25-01024, 2025-01069, 2025-01071, 2025-01665, 2025-
01712, 2025-01713, 2025-01714
Drawings
1-RCS-119
Drawings
1-WCS-56-CD-A
Drawings
PID-25-01C
Engineering P&I Diagram System 053 Reactor Recirculation
Drawings
RBS-ISI-022
Seam Joint ID, Nozzle Location & Weld Map
Miscellaneous
CEP-PT-001
ASME Section XI Pressure Test (PT) Program
313
Miscellaneous
SEP-ISI-RBS-001
Program Section for ASME Section XI, Division 1 RBS
Inservice Inspection Program
Miscellaneous
SEP-PT-001
River Bend Station Inservice Inspection Pressure Testing
(PT) Program Section
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NDE Reports
ISI-VT-08-040
Visual Examination, Component Support-RPV Skirt
2/10/2008
NDE Reports
ISI-VT-17-052
Visual Examination, RPV Skirt
2/16/2017
NDE Reports
RDC-201
JP05 WD-1, Jet Pump Wedge & Wedge Bearing Surface
2/16/2025
NDE Reports
RDC-205
JP02 WD-1, Jet Pump Wedge & Wedge Bearing Surface
2/19/2025
Procedures
CEP-CII-003
Visual Examinations of Class MC Components
309
Procedures
CEP-NDE-0400
Ultrasonic Examination
Procedures
CEP-NDE-0640
Non-Section XI Liquid Penetrant Examination (PT)
Procedures
CEP-NDE-0641
Liquid Penetrant Examination (PT) for ASME Section XI
Procedures
CEP-NDE-0901
VT-1 Examination
Procedures
CEP-NDE-0902
VT-2 Examination
Procedures
CEP-NDE-0903
VT-3 Examination
Procedures
CEP-WP-002
Welding Procedure Specification
Procedures
CEP-WP-004
Control and Documentation of Welding Activities
Procedures
CEP-WP-GWS-1
General Welding Standard ASME/ANSI
Self-Assessments
LO-RBS-2024-
00112
Pre-NRC ISI Activities Self-Assessment Report
11/25/2024
Work Orders
WO- 537913, 593349, 593991. 54116153, 54120602, 54120606
Corrective Action
Documents
CR-RBS-
25-00343
Procedures
Protected Equipment Postings
019
Procedures
STP-203-1702
E22-S001A Bat Performance Discharge Test
26
Work Order
Engineering
Changes
RPV Jet Pump #6 Modification (B-13-PD006-JP6) Main
Wedge Replacement
Procedures
Operability Determination Process
Work Order
Miscellaneous
Out Risk Assessment Team RF-23 Outage Report
Drawings
ESK-11EJS02
480V SWGR Standby Bus UNDV Trip Relays
Engineering
Changes
HVK-CHL1C ECCS Retest
Procedures
Process Applicability Determination
ALARA Plans
RWP 2023-1609
23-1609 Close Out package
06/14/2023
ALARA Plans
RWP 2023-1615
RWP Termination and Post-Job ALARA Review - RWP 2023-
07/17/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1615
ALARA Plans
RWP 2023-1626
23-1626 Close Out package
07/12/2023
ALARA Plans
RWP 2023-1700
23-1700 Close Out package
06/06/2023
ALARA Plans
RWP 2023-1727
23-1727 Close Out package
08/14/2023
ALARA Plans
RWP 2023-1750
23-1750 Close Out package
04/25/2023
ALARA Plans
RWP 2023-1910
23-1910 Close Out package
05/31/2023
ALARA Plans
RWP 2023-1912
23-1912 Close Out package
05/31/2023
ALARA Plans
RWP 2023-1932
23-1932 Close Out package
06/06/2023
ALARA Plans
RWP 2023-1952
23-1952 Close Out package
06/07/2023
ALARA Plans
RWP 2023-1953
23-1953 Close Out package
06/08/2023
ALARA Plans
RWP 2025-1736
ALARA Plan
2/10/2025
ALARA Plans
RWP 2025-1917
ALARA Plan
2/10/2025
Corrective Action
Documents
CR-RBS-
24-02464, 2024-02858, 2024-03755, 2024-03982, 2024-
206, 2024-04217, 2024-04960, 2024-05000, 2024-05544,
24-05751, 2024-05909, 2024-05954, 2024-06181, 2024-
06307, 2025-00208, 2025-00321, 2025-00451, 2025-00672,
25-00721, 2025-00733, 2025-00777, 2025-00798, 2025-
00815, 2025-00853, 2025-00881
Corrective Action
Documents
Resulting from
Inspection
CR-RBS-
25-00895
Miscellaneous
RWP 2023-1609 Dose Dump Report
Miscellaneous
RWP 2023-1700 Dose Dump Report
Miscellaneous
RWP 2023-1912 Dose Dump Report
Miscellaneous
RWP 2023-1952 Dose Dump Report
Miscellaneous
RWP 2023-1953 Dose Dump Report
Miscellaneous
RWP 2023-1910 Dose Dump Report
Miscellaneous
RBS-RPT-24-002
R0
Alpha / Plant Characterization Data
01/31/2024
Procedures
Radiation Worker Expectations
Procedures
Access Control for Radiologically Controlled Areas
Procedures
Radiological Work Permits
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
EN-RP-106-01
Radiological Survey Guidelines
Procedures
Radiation Protection Posting
Procedures
EN-RP-110-03
Collective Radiation Exposure (CRE) Reduction Guidelines
Procedures
EN-RP-110-04
Radiation Protection Risk Assessment Process
Procedures
EN-RP-110-06
Outage Dose Estimating and Tracking
Procedures
Radioactive Material Control
Procedures
Radiological Controls for Highly Radioactive Objects
Procedures
Air Sampling
Procedures
Job Coverage
Procedures
Area Monitoring Program
Procedures
EN-RP141-01
Job Coverage using Remote Monitoring Technology
Radiation
Surveys
7500 RB 186
Refuel Floor blank map showing location of AMS-4s for CR-
Radiation
Surveys
RBS-2023-
Under-vessel radiological surveys from the previous outage:
214, 00303, 00333, 00347, 00386, 00463, 00467, 00530,
00758, 0070, 00781, 00812, 00813, 00834, 00920, 01018,
01169, 01170, 01172, 01214, 01263
Radiation
Surveys
Fuel Building 70' elevation - verification survey of the FB 79'
for unanticipated dose rate alarm
01/14/2025
Radiation
Surveys
Reactor Building 186' - Reactor Cavity Drywell Head
2/11/2025
Radiation
Surveys
DW access 95' equipment hatch
2/15/2025
Radiation
Surveys
Drywell 82' Subpile Room
2/18/2025
Radiation
Surveys
RBS-AS-021125-
0105
Particulate Air Sample, Reactor Building 131', Grab Sample
2/11/2025
Radiation
Surveys
RBS-AS-021225-
0134
Particulate Air Sample, Reactor Building 186', Grab Sample
2/12/2025
Radiation
Surveys
RBS-AS-021225-
0148
Particulate Air Sample, Reactor Building 186', Grab Sample
2/12/2025
Radiation
Surveys
RBS-AS-021325-
0160
Particulate Air Sample, Reactor Building 186', Grab Sample
2/13/2025
Radiation
RBS-AS-021325-
Particulate Air Sample, Reactor Building 186', Grab Sample
2/13/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Surveys
0161
Radiation
Surveys
RBS-AS-021725-
249
Particulate Air Sample, Drywell 82', Grab Sample
2/17/2025
Radiation Work
Permits (RWPs)
25-1736
RF 23 Risk Based - Shielding Installation/Removal Activities
(All Buildings)
Radiation Work
Permits (RWPs)
25-1900
RF 23 Risk Based - Drywell Initial Entry Activities (Includes
DW Unidentified Leak Investigation & VHRA Down-posting
o/s DW)
Radiation Work
Permits (RWPs)
25-1912
Safety Relief Valve (SRV) Activities
Radiation Work
Permits (RWPs)
25-1917
RF 23 Risk Based - Under-Vessel Activities. (including High
Risk Packaging for Shipping)
Radiation Work
Permits (RWPs)
25-1918
RF23 Risk Based - NI Cable Replacement
Radiation Work
Permits (RWPs)
25-1999
RF23 Medium / High Risk - Activities in the Drywell -
Including Insulation Removal and Decon Impacted by Leaks
Self-Assessments
LO-RBS-2024-
00058
IP 71124.01 - Radiological Hazard Assessment and
Exposure Control
11/07/2024
Corrective Action
Documents
CR-RBS-
23-07410, 2024-00751
Corrective Action
Documents
Resulting from
Inspection
CR-RBS-
25-00892, 2025-00896
Miscellaneous
Posi3 USB Test Results Serial Numbers: AMAH196524,
AMAH196535, AMAH196537, AMAH196543, AMAH196548,
AMAH196553, AMAH196563, AMAG199928, AMAG199931,
AMAG204066, and AMAG204085
Miscellaneous
Inspection and Maintenance of Respiratory Protection
Equipment for the month of April 2024
Miscellaneous
Inspection and Maintenance of Respiratory Protection
Equipment for the month of June 2024
Miscellaneous
Inspection and Maintenance of Respiratory Protection
Equipment for the month of September 2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Inspection and Maintenance of Respiratory Protection
Equipment for the month of October 2024
Miscellaneous
240305036-00
Laboratory Report Compressed Air/Gas Quality Testing:
Bauer UNICUS II 030424
03/06/2024
Miscellaneous
240305037-01
Laboratory Report Compressed Air/Gas Quality Testing:
Electric Service Air System SAS-V1416
03/06/2024
Miscellaneous
240618118-01
Laboratory Report Compressed Air/Gas Quality Testing:
Electric Service Air System SAS-V1416
06/19/2024
Miscellaneous
240618119-00
Laboratory Report Compressed Air/Gas Quality Testing:
Bauer UNICUS II 030424
06/19/2024
Miscellaneous
240911011-01
Laboratory Report Compressed Air/Gas Quality Testing:
Electric Service Air System SAS-V1416
09/12/2024
Miscellaneous
240911028-00
Laboratory Report Compressed Air/Gas Quality Testing:
Bauer UNICUS II 030424
09/12/2024
Miscellaneous
FCB T-GET-
RESP
Generic Respiratory Protection Training
Miscellaneous
FPF-GET-RPT
Respiratory Protection Practical Factor Guide
Procedures
Air Sampling
Procedures
Respiratory Protection Program
Procedures
Inspection and Maintenance of Respiratory Protection
Equipment
Procedures
EN-RP-502-01
FireHawk M7 SCBA
Procedures
EN-RP-502-02
Flow Testing MSA Breathing Apparatus
Procedures
EN-RP-502-03
AirHawk II SCBA
Procedures
Selection, Issue and Use of Respiratory Protection
Equipment
Procedures
Breathing Air
Procedures
EN-RP-504-01
UNICUS II Operating Instructions
Procedures
PortaCount Respirator Fit Testing
Radiation Work
Permits (RWPs)
251917
RF 23 Risk Based - Undervessel Activities (including High
Risk Packaging for Shipping)
Self-Assessments
LO-RBS-2024-
00058
Focused Self-Assessment/Formal Benchmark Report:
RIVER BEND - IP 71124.01 - Radiological Hazard
Assessment and Exposure Controls, IP 71124.03 - In-Plant
11/07/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Airborne Radioactivity Control and Mitigation, IP 71151 - PI
Verification
Self-Assessments
LO-RBS-2024-
00078-00001
21 - 2023 Triennial Respiratory Program Report, Radiation
Protection - River Bend Station
2/17/2024
Self-Assessments
LO-RLO-2023-
00043
Radiation Protection High Efficiency Particulate Air (HEPA)
Program - River Bend
71151
Miscellaneous
RBG-48276
River Bend Nuclear Station Annual Radioactive Effluent
Release Report 2023
04/16/2024
71151
Work Orders
Work Order (WO)
RPP-0102: Dose Calculation from Gaseous Effluents -
54101888-01, 54113677-01, 54125667-01, 54136605-01,
54146423-01, 54154660-01, 54165481-01, 54178412-01,
54189653-01, 54204234-01, 54214897-01, 54224771-01
71151
Work Orders
Work Order (WO)
RPP-0097: Manual Method of Determining Cumulative Dose
Due to Liquid Effluents - 54101934-01, 54115416-01,
54125701-01, 54136661-01, 54146236-01, 54154702-01,
54165523-01, 54178435-01, 54189680-01, 54204271-01,
214947-01, 54224821-01
Corrective Action
Documents
CR-RBS-
24-05965, 2025-00670, 2025-01221
Procedures
Work Orders