IR 05000440/2025003
| ML25363A061 | |
| Person / Time | |
|---|---|
| Site: | Perry |
| Issue date: | 12/29/2025 |
| From: | Sanchez E NRC/RGN-III/DORS/RPB2 |
| To: | Tony Brown Vistra Operations Company |
| References | |
| IR 2025003 | |
| Download: ML25363A061 (0) | |
Text
SUBJECT:
PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000440/2025003
Dear Terry Brown:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Perry Nuclear Power Plant. On December 4, 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.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the regional offices an extension on the issuance of the calendar year 2025, third quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, fourth quarter integrated inspection reports, which will be issued 45 days after the fourth quarter ends on December 31, 2025.
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.
December 29, 2025 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 III; the Director, Office of Enforcement; and the NRC Resident Inspector at Perry Nuclear Power Plant.
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 III; and the NRC Resident Inspector at Perry Nuclear Power Plant.
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, Elba M. Sanchez Santiago, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety Docket No. 05000440 License No. NPF-58 Enclosure:
As stated cc: Distribution via LISTSERV Signed by Sanchez Santiago, Elba on 12/29/25
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Perry Nuclear Power Plant, 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
Misconfiguration of the Drywell Atmosphere Radiation Monitor Sample Path Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000440/202500301 Open/Closed
[H.12] - Avoid Complacency 71152A A Green finding and associated non-cited violation (NCV) of Technical Specification (TS)5.4.1.a, Procedures, was self-revealed when the licensee failed to follow the procedure step-by-step during the execution of work order (WO) 200972359, resulting in a misconfiguration and invalid drywell atmosphere grab sample.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at full power. On July 18, 2025, the unit was reduced to approximately 85 percent power for emergent non-safety system maintenance. On July 20, 2025, the unit was returned to rated power. On September 5, power was reduced to 85 percent power for planned safety system maintenance. That was followed by further power reduction to approximately 60 percent power for turbine and steam system testing and rod pattern adjustment. On September 8, power was restored to rated power. The plant operated at or near rated thermal power for the remainder of the inspection period with occasional power derates related to heat and humidity.
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
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (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) Turbine building 577' elevation
- (2) Unit 1 auxiliary building
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced drill on September 3, 2025
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 division 3 work on September 29 and 30, 2025
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated operator requalification simulator performance on July 28, 2025
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Steam tunnel ventilation and leak detection instrumentation
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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) Risk of using a non-credited data source on the plant computer system while the engineering change (ECP) is implemented for the execution and validation of data on planned work on the week ending on September 26, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Hydraulic control unit 5839
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) Installation of test switch into the division 2 safety relief valve circuitry, completed the week ending July 12, 2025
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) Division 2 anticipated transient without scram uninterruptible power supply after corrective maintenance on August 28, 2025
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Type C local leak rate test of 1D17 penetration P201D17F071B for work order (WO)
2009677423 on April 11, 2025 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02)
- (1) FLEX 4160-volt distribution center functional test for WO 200903461 on September 22, 2025
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.0102.04) (1 Sample)
- (1) The inspectors evaluated the following maintenance and testing of the alert and notification system:
- Annual siren inspection and maintenance records for the period from October 1, 2024, through December 31, 2024
- Weekly alert notification system (siren) tests for the period from October 1, 2024, through December 31, 2024
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.0102.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the emergency preparedness organization
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Full scale emergency preparedness drill on September 17,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
Groundwater Protection Initiative (GPI) Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the (GPI) program to identify incomplete or discontinued program elements.
OTHER ACTIVITIES-BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 (July 1, 2024 through September 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) Unit 1 (July 1, 2024 through September 30, 2025)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) Unit 1 (July 1, 2024 through September 30, 2025)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) Unit 1 (July 1, 2024 through June 30, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) Unit 1 (July 1, 2024 through September 30, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2024 through June 30, 2025 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) October 1, 2024 through June 30, 2025
EP01: Drill/Exercise Performance Sample (IP Section 02.12) (1 Sample)
- (1) Unit 1 (July 1, 2024 through June 30, 2025)
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) Unit 1 (July 1, 2024 through June 30, 2025)
EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)
- (1) Unit 1 (January 1, 2025 through June 30, 2025)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
- (1) Misconfiguration of the drywell atmospheric monitoring system
OTHER ACTIVITIES
-TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
92709 - Licensee Strike Contingency Plans Licensee Strike Contingency Plans
- (1) On August 31, 2025, at midnight, the contract between IBEW 270 expired. In preparation for potential strike, the NRC inspectors evaluated the adequacy of the licensees contingency plan. The inspectors assessed the adequacy of the plans post strike staffing levels, staff qualifications, safety conscious working environment, and site access in meeting operational and security requirements.
INSPECTION RESULTS
Misconfiguration of the Drywell Atmosphere Radiation Monitor Sample Path Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000440/202500301 Open/Closed
[H.12] - Avoid Complacency 71152A A Green finding and associated non-cited violation (NCV) of Technical Specification (TS)5.4.1.a, Procedures, was self-revealed when the licensee failed to follow the procedure step-by-step during the execution of Work Order (WO) 200972359, resulting in a misconfiguration and invalid drywell atmosphere grab sample.
Description:
With the reactor plant in Mode 1, the drywell process flow radiation monitor became inoperable per TS 3.4.7, due to a failed primary containment isolation valve on the suction side of the monitor on April 26, 2025. From that date through June 10, 2025, valid grab samples of the drywell atmosphere were obtained once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> fulfilling TS 3.4.7.B.1, Required Action.
On June 11, 2025, repairs to the drywell radiation monitor suction isolation valve were completed and a post maintenance local leak rate test (LLRT) was executed per WO 200972359. However, a misconfiguration of the drywell atmosphere radiation monitor sample path occurred during the pre-test evolution. The licensee erroneously removed the spool piece on the drywell atmosphere radiation monitor performed which was not a step delineated in WO 200972359. As a result, an unknown loss of configuration control of the drywell atmosphere grab sample path occurred that invalidated the June 11, 2025, TS 3.4.7.B.1, Required Action, grab samples of the drywell atmosphere.
On June 12, 2025, it was discovered that the June 11 TS 3.4.7.B.1 grab samples of the drywell atmosphere were not sampling the drywell atmosphere as assumed due to the misconfiguration during the LLRT. This was self evident as the isotopic mix was not indicative of the drywell atmosphere. At this point is when both the licensee and the NRC inspectors became aware of the problem. After further investigation, the spool piece for the drywell process flow radiation monitor return line was found removed when it should have been installed. The reactor coolant system leakage was unchanged from previous shifts and indicated no leakage. The operating crew exercised TS surveillance requirement (SR) 3.0.3, which allows up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform surveillance prior to declaring LCO 3.4.7, Condition B not met. After verifying the drawing with unit supervisor which spool piece was to be reinstalled, mechanical supervision briefed mechanics and directed the reinstallation of the discharge side spool piece. The drywell atmospheric grab sample was completed at 1731 with satisfactory results fulfilling TS 3.4.7.B.1, Required Action. Later, on June 12, 2025, the drywell process flow radiation monitor was declared operable and associated LCO 3.4.7, Condition B exited.
The licensee conducted an apparent cause evaluation of the adverse condition contributing the apparent cause to organizational gradual variation and determined that over time, procedural rigor, responsibility expectations, and configuration consistency were not consistently emphasized, allowing informal task execution behaviors to become normalized and proceed without correction even during configuration-sensitive work. This is in line with the inspectors behavior assessment of complacency in which the individuals failed to recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes.
Corrective Actions: Upon discovery, the licensee restored configuration and completed TS 3.4.7.B.1, Required Action. Additionally, the licensee entered the issue into their corrective action program and created corrective actions to restore supervisory engagement, reinforce human performance expectations, and embed oversight behaviors that ensure task readiness and procedural adherence are verified before work begins.
Corrective Action References: CR202504350
Performance Assessment:
Performance Deficiency: The licensees failure to perform repairs to the drywell radiation monitor suction isolation valve in accordance with WO 200972359, which resulted in a configuration control issue, was a performance deficiency that warranted further evaluation.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the SSC and Barrier Performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. The inspectors compared the issue to the examples and guidance in IMC 612, Appendix E, Examples of Minor Issues, and determined that the issue was similar to example 3.d of Appendix E. Specifically, the performance deficiency impacted the barrier integrity cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by coolant system leakage by removing the ability to monitor the drywell atmosphere.
Significance: 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 Exhibit 3, Barrier Integrity Screening Questions, Section B, Reactor Coolant System (RCS) Boundary. The inspectors answered no to the questions, which resulted in a Green characterization of the issue.
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. Although this task was recently performed in the previous refueling outage, the plant conditions and worker assumptions had changed. These points were detailed in the revised work order that was not referenced during the system configuration misalignment. The individual and supervision of the maintenance failed to apply error reduction tools to plan for the possibility of mistakes, latent issues, and inherent risk of the maintenance task.
Enforcement:
Violation: TS 5.4.1, Procedures, requires that written procedures shall be established, implemented, and maintained as recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Regulatory Guide 1.33, Appendix A, Section 9, Procedures for Performing Maintenance, specifically addresses the need to have appropriate written procedures, documented instructions, or drawings appropriate for maintenance that can affect the performance of safety-related equipment.
The licensee established procedure WO 200972359 to perform repairs to the drywell monitoring system. Operation 310, Step 1. of the work order states, REMOVE test flanges from suction line, clean gasket surfaces.
Contrary to the above, on June 11, 2025, the licensee failed to implement Operation 310, Step 1, of WO 200972359. Specifically, the licensee failed to remove test flanges from the suction line and instead removed both the suction line and discharge line test flanges. As a result, an unknown loss of configuration control of the drywell atmosphere grab sample flow path occurred that rendered TS 3.4.7.B.1, "Required Action," grab samples of the drywell atmosphere invalid.
Enforcement Action: This violation is being treated as a NCV, 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 December 4, 2025, the inspectors presented the integrated inspection results to T. Brown, Site Vice President, and other members of the licensee staff.
- On August 25, 2025, the inspectors presented the radiation protection inspection results to D. Benyak, Plant General Manager, and other members of the licensee staff.
- On September 29, 2025, the inspectors presented the emergency preparedness inspection results to T. Brown, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP1AB
Aux Building Unit 1
FPI1TB
Turbine Building 577'
Fire Plans
FPI-AB02
Fire Brigade Drills
Work Orders
200970659
RHR Heat Exchangers B and D Performance Testing
07/14/2025
FLT-OPRM1002
Conduct of Operations
Miscellaneous
NOBP-TR1112
Conduct of Simulator Training and Evaluation
CR202504480
Unseasonably High Steam Tunnel Temps
06/19/2025
Corrective Action
Documents
CR202504790
Elevated Steam Tunnel Temperature IOI15 Guidance
07/02/2025
CR202506791
25 Cybersecurity NRC Inspection-Cybersecurity
Vulnerability Assessment Process Did Not Identify Common
Vulnerability and Exposure for Software on CDA
09/25/2025
CR202506803
25 Cybersecurity NRC Inspection - Plant Computer
Upgrade
09/25/2025
Corrective Action
Documents
Resulting from
Inspection
CR202506809
25 Cybersecurity NRC Inspection - Plant Computer System
Firewalls Installed Without a Workorder Step
09/25/2025
Corrective Action
Documents
CR202506292
Rod Drift for Control Rod 5839 from Position 48 to Position 32
09/06/2025
B2080011-
00012
Automatic Depressurization System ADS Valves
S
B208011-C01
Automatic Depressurization System Notes, References, and
Switch Tabulations
M
Drawings
PDUN 241019-
2001
Update to Drawing 2080011-00004
Engineering
Changes
241019-002
Div 2 SRV Test Switch Modification
Procedures
SVI-B21T0369B
SRV and Low-Low Set Pressure Actuation Channel Functional
for 1B21N668B
Work Orders
200949369
Implement ECP 241019-002 Div 2 SRV Bypass Switch
07/08/2025
Procedures
SVI-D17T9201
Type C Local Leak Rate Test of 1D17 Penetration P201
200903461
FLEX 4160V Distribution Center Functional Test
09/03/2025
Work Orders
200967423
Post-Maintenance Testing of D17F071B
04/11/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200979250
Division 2 ATWS UPS Normal Power Supply
08/28/2025
CR202408741
MSC2411-24: Incomplete ANS Siren Test Reports
11/07/2024
CR202501138
Siren L23 Indicated a Rotation Failure on the 2/20/2025 Siren
Test
2/20/2025
Corrective Action
Documents
CR202501719
Emergency Response Office Siren Computer Failure
03/12/2025
0100054
Tempest T112/T121 Omni-Directional Siren Installation,
Operation, and Service Manual
H
Test Data
25 Quarterly Siren Test Data
01/01/2025-
2/31/2025
Miscellaneous
Test Data
24 Quarterly Siren Test Data
01/01/2024-
2/31/2024
NOBP-LP5018
Siren Testing and Maintenance
Procedures
NOP-LP5005
Siren Testing and Maintenance
CR2024051888
Employee Did Not Respond to ERO Unannounced Call-in Drill
06/17/2024
CR202406853
Maintenance Craft Everbridge Notification
08/27/2024
CR202503481
1st Quarter Unannounced ERO Call-In Drill Not Performed
Within 1st Quarter
05/06/2025
Corrective Action
Documents
CR202504466
Missed Scheduled EPlan Phone Test
06/18/2025
Emergency Response Organization Training and Qualification
Records (Spot-Checked, 22 ERO Records in LMS)
09/10/2025
EP0000
Emergency Plan for Perry Nuclear Power Plant
Miscellaneous
Staffing Analysis
Perry Nuclear Power Plant, OnShift Staffing Analysis
NOP-LP5006
Emergency Response Organization Training Program
NOP-LP5505
Facility Activation, Operation and DeActivation
Procedures
PTI-GEN-P0003
Quarterly Testing of the Emergency Notification System
MSC2311-24
Quality Assurance Audit Report (Emergency Preparedness)
11/13/2023-
2/18/2023
Miscellaneous
MSC2411-24
Nuclear Oversight Audit Report, Emergency Preparedness
(EVAL2024006)
11/04/2024-
2/18/2024
Procedures
PYBY-ERS0003
Emergency Plan Facility/Equipment Inventory Checklists
Self-Assessments
FLT-PIPB1220
Self-Assessments
06/05/2025
REMP Air Sampler 7018 Calibration
08/12/2025
Calibration
Records
REMP Air Sampler 7002 Calibration
08/12/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR202404905
UPS Disposed of REMP Water Samples
06/04/2024
CR202505072
REMP Vegetation Unavailable for July Sampling
07/15/2025
Corrective Action
Documents
CR202505872
Control Garden Participant Dropped from the REMP
08/18/2025
Corrective Action
Documents
Resulting from
Inspection
CR202505900
ODCM Table and AREOR Table Incorrect Units for Reporting
Sediment
08/19/2025
8033101-286
Microbac Laboratory Results for Groundwater Samples
2/14/2024
8033101-290
Microbac Laboratory Results for Groundwater Samples
04/15/2024
L24096
23 Annual Radiological Environmental Operating Report
04/22/2024
L25065
24 Annual Radiological Environmental Operating Report
04/28/2025
L25066
24 Annual Radiological Effluent Release Report
04/28/2025
Miscellaneous
Offsite Dose Calculation Manual
REMP0009
Surface and Drinking Water Sampling
Procedures
REMP0023
Air Sample Collection
200903518
Met Tower Air Temperature Calibration
05/01/2025
200903572
Met Tower 10 Meter Wind Direction Calibration
05/06/2025
200903573
Met Tower 60 Meter Wind Speed Calibration
10/30/2024
200903576
Met Tower 60 Meter Wind Direction Calibration
05/04/2025
Work Orders
200903577
Met Tower 10 Meter Wind Speed Calibration
10/29/2024
Occupational Exposure Control Effectiveness Performance
Indicator Package
11/04/2024
Occupational Exposure Control Effectiveness Performance
Indicator Package
2/03/2025
Occupational Exposure Control Effectiveness Performance
Indicator Package
04/01/2025
NRC Performance
Indicator Data
Emergency Preparedness - Drill/Exercise Performance
06/30/2025
NRC Performance
Indicator Data
Emergency Preparedness - ERO Readiness
06/30/2025
NRC Performance
Indicator Data
Emergency Preparedness - Alert and Notification System
Reliability
06/30/2025
71151
Miscellaneous
NRC Performance NRC Performance Indicator Data MS08 Heat Removal
06/30/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Indicator Data
Systems
NRC Performance
Indicator Data
NRC Performance Indicator Data MS09 Residual Heat
Removal Systems
06/30/2025
NRC Performance
Indicator Data
NRC Performance Indicator Data MS10 Cooling Water
Support Systems
06/30/2025
NRC Performance
Indicator Data
NRC Performance Indicator Data BI02 RCS Leak Rate
Sample
06/30/2025
Corrective Action
Documents
CR202504350
Misconfiguration of the D17 Drywell Atmosphere Radiation
Monitor Sample Path
08/04/2025