ML25363A061
| 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
Terry Brown Site Vice President Vistra Operations Company, LLC Perry Nuclear Power Plant 10 Center Road Perry, OH 44081
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
T. Brown 2
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
T. Brown 3
Letter to Terry Brown from Elba Sanchez Santiago dated December 29, 2025.
SUBJECT:
PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000440/2025003 DISTRIBUTION:
Rodney Clagg RidsNrrPMPerry Resource RidsNrrDorlLpl3 RidsNrrDroIrib Resource Jack Giessner Mohammed Shuaibi Diana Betancourt-Roldan John Pelchat Deborah Piskura Jared Heck Jennifer Dalzell R3-DORS ADAMS Accession Number: ML25363A061
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII NAME ESanchezSantiago:
gmp DATE 12/29/2025 OFFICIAL RECORD COPY
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000440 License Number:
NPF-58 Report Number:
05000440/2025003 Enterprise Identifier:
I2025003-0050 Licensee:
Vistra Operations Company, LLC Facility:
Perry Nuclear Power Plant Location:
Perry, OH Inspection Dates:
July 01, 2025 to September 30, 2025 Inspectors:
J. Beavers, Senior Resident Inspector T. McGowan, Emergency Preparedness Inspector V. Myers, Senior Health Physicist R. Ng, Senior Project Engineer T. Ospino, Resident Inspector T. Taylor, Senior Resident Inspector Approved By:
Elba M. Sanchez Santiago, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety
2
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.
3 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
4 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
5 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 Sample)
(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, 2025
6 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 Sample)
(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
7 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 Sample)
(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 Sample)
(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.
8
==
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
9 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.
10 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.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date FP1AB Aux Building Unit 1 4
FPI1TB Turbine Building 577' 0
71111.05 Fire Plans FPI-AB02 Fire Brigade Drills 9
71111.07A Work Orders 200970659 RHR Heat Exchangers B and D Performance Testing 07/14/2025 FLT-OPRM1002 Conduct of Operations 0
71111.11Q Miscellaneous NOBP-TR1112 Conduct of Simulator Training and Evaluation 17 CR202504480 Unseasonably High Steam Tunnel Temps 06/19/2025 71111.12 Corrective Action Documents CR202504790 Elevated Steam Tunnel Temperature IOI15 Guidance 07/02/2025 CR202506791 2025 Cybersecurity NRC Inspection-Cybersecurity Vulnerability Assessment Process Did Not Identify Common Vulnerability and Exposure for Software on CDA 09/25/2025 CR202506803 2025 Cybersecurity NRC Inspection - Plant Computer Upgrade 09/25/2025 71111.13 Corrective Action Documents Resulting from Inspection CR202506809 2025 Cybersecurity NRC Inspection - Plant Computer System Firewalls Installed Without a Workorder Step 09/25/2025 71111.15 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 241019-002001 Update to Drawing 2080011-00004 0
Engineering Changes 241019-002 Div 2 SRV Test Switch Modification 0
Procedures SVI-B21T0369B SRV and Low-Low Set Pressure Actuation Channel Functional for 1B21N668B 11 71111.18 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 11 200903461 FLEX 4160V Distribution Center Functional Test 09/03/2025 71111.24 Work Orders 200967423 Post-Maintenance Testing of D17F071B 04/11/2025
12 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 02/20/2025 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
Perry EPZ Siren Test Data 2025 Quarterly Siren Test Data 01/01/2025-12/31/2025 Miscellaneous Perry EPZ Siren Test Data 2024 Quarterly Siren Test Data 01/01/2024-12/31/2024 NOBP-LP5018 Siren Testing and Maintenance 4
71114.02 Procedures NOP-LP5005 Siren Testing and Maintenance 1
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 61 Miscellaneous Staffing Analysis Perry Nuclear Power Plant, OnShift Staffing Analysis 1
NOP-LP5006 Emergency Response Organization Training Program 8
NOP-LP5505 Facility Activation, Operation and DeActivation 2
71114.03 Procedures PTI-GEN-P0003 Quarterly Testing of the Emergency Notification System 16 MSC2311-24 Quality Assurance Audit Report (Emergency Preparedness) 11/13/2023-12/18/2023 Miscellaneous MSC2411-24 Nuclear Oversight Audit Report, Emergency Preparedness (EVAL2024006) 11/04/2024-12/18/2024 Procedures PYBY-ERS0003 Emergency Plan Facility/Equipment Inventory Checklists 26 71114.05 Self-Assessments FLT-PIPB1220 Self-Assessments 06/05/2025 REMP Air Sampler 7018 Calibration 08/12/2025 71124.07 Calibration Records REMP Air Sampler 7002 Calibration 08/12/2025
13 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 02/14/2024 8033101-290 Microbac Laboratory Results for Groundwater Samples 04/15/2024 L24096 2023 Annual Radiological Environmental Operating Report 04/22/2024 L25065 2024 Annual Radiological Environmental Operating Report 04/28/2025 L25066 2024 Annual Radiological Effluent Release Report 04/28/2025 Miscellaneous ODCM Offsite Dose Calculation Manual 25 REMP0009 Surface and Drinking Water Sampling 10 Procedures REMP0023 Air Sample Collection 8
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 02/03/2025 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
14 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 71152A Corrective Action Documents CR202504350 Misconfiguration of the D17 Drywell Atmosphere Radiation Monitor Sample Path 08/04/2025