IR 05000440/2025002
| ML25218A020 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/07/2025 |
| From: | Sanchez-Santiago E NRC/RGN-III/DORS/RPB2 |
| To: | Tony Brown Vistra Operations Company |
| References | |
| IR 2025002 | |
| Download: ML25218A020 (1) | |
Text
SUBJECT:
PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000440/2025002
Dear Terry Brown:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Perry Nuclear Power Plant. On July 16, 2025, the NRC inspectors discussed the results of this inspection with D. Benyak, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Elba M. Sanchez Santiago, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety Docket No. 05000440 License No. NPF-58
Enclosure:
As stated
Inspection Report
Docket Number:
05000440
License Number:
Report Number:
Enterprise Identifier:
I-2025-002-0050
Licensee:
Vistra Operations Company, LLC
Facility:
Perry Nuclear Power Plant
Location:
Perry, OH
Inspection Dates:
April 01, 2025 to June 30, 2025
Inspectors:
J. Beavers, Senior Resident Inspector
N. Day, Senior Resident Inspector
T. Ospino, Senior Resident Inspector
Approved By:
Elba M. Sanchez Santiago, Chief
Reactor Projects Branch 2
Division of Operating Reactor Safety
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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000440/2025 001-00 LER 2025001-00 for Perry Nuclear Power Plant, Automatic Actuation of Division 3 Diesel Generator Resulting from Startup Transformer Testing 71153 Closed
PLANT STATUS
Unit 1 began the inspection period shut down in a refueling outage. On April 14, 2025, the outage was completed and power restored to rated thermal power. On June 28, 2025, the unit was reduced to 65 percent to adjust rod line. On June 30, 2025, the unit was restored to rated thermal 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
71111.01 - 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 seasonal hot temperatures for the main steam tunnel ventilation, turbine building chilled water system, and auxiliary building ventilation systems on June 20, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Control rod drive hydraulic train 'B' before startup operations on April 19, 2025
- (2) Reactor core isolation cooling system after maintenance on April 19, 2025
- (3) Fuel pool cooling and cleanup system after fuel offload on June 26, 2025
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) High pressure core spray during the week of April 7, 2025
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) Unit 1 turbine building on April 2, 2025
- (2) Auxiliary building steam tunnel on April 9, 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 announced fire drill on May 14, 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 reactor plant startup on April 20 and 21, 2025
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated operator requalification simulator performance on May 5, 2025
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Outboard main steam isolation valve 'D' failure on April 6, 2025
- (2) Reactor recirculation pump 'A' flow control valve failure on April 6, 2025
- (3) Reactor recirculation pump 'B' flow control valve failure on April 7, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Risk associated with the turbine overspeed test malfunction on May 3, 2025
- (2) Risk associated with the main transformer 'C' cooling groups 1 and 4 issues on May 8, 2025
- (3) Division 1 work week planned activities during the week ending May 16, 2025
- (4) Division 2 work week planned activities to include division 1 heating and ventilation outage during the week ending May 23, 2025
- (5) Emergency service water system 'A' medium risk activities and associated 72-hour technical specifical limiting conditions of operation during the week ending June 20, 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) Operability determination verification of mode restraint list and readiness for entry into Mode 4 on April 10, 2025
- (2) Operability determination of intermediate range instruments 'C' and 'E' due to failed linearity checks during reactor plant startup on April 20, 2025
- (3) Operability determination of offgas pretreatment radiation monitor on April 22, 2025
- (4) Operability determination of division 2 emergency diesel generator during the week ending on May 23, 2025
- (5) Operability determination of the offgas pretreat system during the 1R20 outage on June 9, 2025
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) Permanent modification of the reactor protection system power selector switch
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage activities from April 1, 2025, to April 21, 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) (13 Samples)
- (1) Replacement of hydramotor 1D17F0071B as a result of a failed stroke time close on March 12. 2025
- (2) Replacement of the high voltage fuse and the challenges returning transformer LH2A to service on March 27, 2025
- (3) Low pressure core spray injection valve work on March 29, 2025
- (4) Low pressure core spray and 'A' residual heat removal (RHR) waterleg pump test on March 29, 2025
- (5) Drywell airlock test during the 1R20 outage
- (7) Reactor core isolation cooling steam supply inboard and outboard valves following maintenance on April 10, 2025
- (8) Main steam isolation outboard 'A' air drop test after test failure on April 13, 2025
- (9) Main steam isolation inboard valve 'A' VT2 during reactor pressure vessel test on April 16, 2025
- (10) Reactor recirculating pump suction valve VT2 during reactor pressure vessel test on April 16, 2025
- (11) Main steam isolation inboard drain valve VT2 during reactor pressure vessel test on April 16, 2025
- (12) Reactor recirculating pump 'B' flow control valve VT2 during reactor pressure vessel test on April 16, 2025
- (13) Outboard main steam isolation valve 'A' local leak rate testing (LLRT) and other tests after issues with it on June 11, 2025
Surveillance Testing (IP Section 03.01) (7 Samples)
- (1) Division 3 diesel generator start and load on March 28, 2025
- (2) Division 1 retest of the loss of offsite power/ loss of coolant accident (LOOP/LOCA)testing on April 1, 2025
- (3) Fire suppression valve cycle on April 3, 2025
- (5) Unit 2 transformer insulation resistance checks on April 10, 2025
- (6) Intermediate range monitoring voltage calibration on April 20, 2025
- (7) Unit 2 main transformer double testing on April 23, 2025
Inservice Testing (IST) (IP Section 03.01) (3 Samples)
- (1) Shutdown cooling suction isolation valve operability test on March 28, 2025
- (2) Low pressure core spray isolation valve leak rate test on March 30, 2025
- (3) Reactor coolant system leakage pressure test on April 16, 2025
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) Full scale emergency response organization drill on June 11,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2024 through March 31, 2025)
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) Unit 1 (April 1, 2024 through March 31, 2025)
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) Unit 1 (April 1, 2024 through March 31, 2025)
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) Onsite storage container radioactive leak
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in equipment reliability that might be indicative of a more significant safety issue.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)
- (1) On June 11, 2025, an individual found smoke in warehouse 6, which is located inside the licensee's owner-controlled area but outside the protected area. The control room was immediately notified and Off Normal Instruction ONI-P54, Fire, was entered and 911 was called to initiate offsite firefighting response. The control room directed the starting of the motor fire pump and immediate notification of site personnel including the resident inspectors. The site fire brigade remained on standby as per agreements with local firefighting agencies as this building was outside of the protected area fence and required no special access to mitigate the fire. Licensee personnel remained in contact with the local firefighting agency efforts and were available to deenergize the building as required by the incident commander, which was not requested. Inside the warehouse, a limited area fire was identified and mitigation commenced. Damaged and burned materials were removed to the parking lot and thoroughly wetted. The fire was extinguished within an hour of offsite response.
No personnel were injured during this event, and no ambulance response was required. The same day the off normal instruction was exited and the fire system restored to standby. The affected warehouse contained materials to support plant operation and maintenance activities. No hazardous materials were identified as impacted, and the building contained no radioactive material.
The inspectors determined the event did not meet any emergency action level entry criteria due to the fires location being outside of the protected area, and the fact that the fire did not impact the safety and security of the power plant or its operations.
Additionally, no nuclear regulatory reporting actions were required. The inspectors did not identify any issues associated with the licensees response.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2025001, Automatic Actuation of Division 3 Diesel Generator Resulting from Startup Transformer Testing. (ADAMS Accession No. ML25141A212)
The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is Closed.
INSPECTION RESULTS
Observation: Onsite Storage Container Radioactive Leak 71152A The inspectors performed an indepth review of the October 14, 2024, onsite storage container radioactive leak event cause and corrective action progress as of June 30, 2025.
This sample was selected as a timely review of the event with potential public impact and interest previously dispositioned in the Perry Integrated Inspection Report 05000440/2024004 (ML25042A066).
The licensee's analysis determined site personnel made assumptions that the shield container was suitable for outdoor storage without verification in contrast to the requirements of site procedures. This conclusion was supported by: the site not procuring the necessary equipment or plan for how to handle the liner after it was depleted to ensure safe, timely handling, storage, and disposal; inadequate information regarding the suitability of the shield container for outdoor storage in the work order, procedures, or other instructions; and failure to stop in the face of uncertainty when trying the set the shield plug into place. These issues were dispositioned in the aforementioned inspection report.
The licensees corrective actions included the completed immediate actions of securing the leak source and radioactive mitigation of the affected area. The plan to track and clean up the onsite storage container yard has been approved and largely completed with the majority of the contaminated soil shipped offsite and the remainder of the soil and sealed source liner prepared for imminent transport. The documentation and process changes have been largely completed, including the update of 10CFR50.75(g) for use in eventual plant decommissioning activities. The remaining items include the identification and fabrication of a new location for onsite storage of radiological waste awaiting transport.
The inspectors evaluated the licensees onsite storage container radioactive leak cause and corrective action effort and identified no more than minor findings or violations.
Observation: Trend in Equipment Reliability 71152S The inspectors performed a semiannual review of a potential adverse trend in the licensees equipment reliability issues that might be indicative of a more significant safety issue. The following corrective action documents were associated with this review:
1. CR 202501258, Unplanned Reactor Shutdown
2. CR 202501429, Equipment Reliability Challenge Board: Perry is projected to have
incurred INPO Noteworthy Consequential Events in each of the last four months
3. CR 202503352, Perry Escalation - Equipment Reliability
4. CR 202403861, Equipment Reliability Challenge Board: Corrective Action Program
During the inspection period, the inspectors evaluated corrective action program entries related to equipment reliability. They were chosen for inspection sample due to their relation to an increased number of forced outages and down powers. The primary events evaluated were turbine trip on loss of vacuum, forced outage due to circulating water system leak, significant down power to stator cooling water system outage, and recirculating water system flow issues on non-safety systems. These events resulted in significant power transients and initiating event cornerstone challenges, driving abnormal plant configurations and increased risk. The licensee also performed a review of this trend and identified a concern of not leveraging the corrective action program for issue identification may lead to the lack of cross functional team knowledge, understanding, challenge, and correction of equipment reliability issues. The licensee further stated that Relative to the number consequential events that have occurred at Perry, promotion and reinforcement of a lower corrective action program issue initiation threshold may be required. The licensee documented these conclusions in CR202503861.
The inspectors performed their review in accordance with the inspection procedure and trended the behavior to consider potential safety culture weaknesses. Based on their review they noted a trend associated with CO.4 Expectations: Leaders frequently communicate and reinforce the expectation that nuclear safety is the organizations overriding priority.
Specifically, executives and senior managers reinforce the importance of nuclear safety by clearly communicating its relationship to strategic issues including budget, workforce planning, equipment reliability, and business plans, as defined in NUREG 2165, Safety Culture Common Language. The inspectors provided this feedback to the licensee to ensure they were taking the necessary actions to address the identified trend. This review focused on the corrective action program aspects of the issues. No performance deficiencies were identified as a result of this review.
Minor Performance Deficiency 71153 LER 2025001-00 for Perry Nuclear Power Plant, Automatic Actuation of Division 3 Diesel Generator Resulting from Startup Transformer Testing Minor Performance Deficiency: On March 29, 2025, Unit 1 was in Mode 5 during a refueling outage with a single offsite power source available through the Unit 1 startup transformer.
During testing of the Unit 2 startup transformer, power was disrupted to the available but inoperable division 3 shutdown safety electrical bus. This caused an actuation of the division 3 emergency diesel generator (3DG) system and entries into off normal operating procedures for the following systems: electrical power, non-safety service water, and the plant air system.
Both the licensee and the NRC resident inspectors became aware of the issue immediately.
This event was reported at 1616 on March 29, 2025, as a 10 CFR 50.72(b)(3)(iv)(A) event resulting in a valid actuation of the emergency diesel generator system.
During the investigation process, the licensee identified relay testing associated with a startup transformer tripped a switch interlock on the breaker that had been energizing the 13.8 kV bus feeding the division 3 shutdown safety electrical bus. They also identified they performed insufficient impact and work order reviews of transformer relay testing. Additionally, engineering provided erroneous technical information regarding breaker control schematics and engineering did not perform a review of a work order revision with the tests steps.
Corrective actions included training on electrical interlocks and relay schemes, installing a caution placard on a breaker door, issuing of a night order to operators regarding lessons learned, and incorporating this operating experience into a work order for similar work in the next refueling outage.
The failure to properly review the transformer relay testing impact and work order sufficiently during the planning phase of the work management process was contrary to the licensee's Work Management Process procedure, NOP-WM-0001. The inspectors determined this failure was a performance deficiency. No violation of NRC requirements was identified during this review.
Screening: The inspectors determined the performance deficiency was minor. Though the performance deficiency was associated with the mitigating systems cornerstone attribute of human performance, it did not adversely affect the associated cornerstone objective.
Specifically, the 3DG and its supported high pressure core spray pump system were already inoperable to support maintenance and not needed to meet technical specification (TS)requirements. Additionally, both division 1 and division 2 emergency diesel generators and residual heat removal 'B' and 'C' emergency core cooling systems (ECCS) were operable to satisfy ECCS TS 3.5.2 requirements for Modes
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 16, 2025, the inspectors presented the integrated inspection results to D. Benyak, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
IOI0015
Seasonal Variations
VLI-C11 (CRDH)
Control Rod Drive Hydraulic System (CRDH)
VLI-E22A
VLI-E51
Reactor Core Isolation Cooling System
Procedures
VLI-G41 (FPCC)
Fuel Pool Cooling and Cleanup System
06/26/2025
FPI1ST
Steam Tunnel
04/09/2025
Fire Plans
FPI1TB
Turbine Building Unit 1
Procedures
FD 1450051425
MB100 2nd Floor Classroom
05/14/2025
Procedures
IOI0001
Cold Startup
CR202502066
Recirc Pump 'A' Discharge Valve Handwheel Broken
03/24/2025
CR202502528
MSL 'A' OTBD MSIV Leakage Exceeds Allowable Limit
04/06/2025
CR202502551
FCV 'B' Will Not Stroke Open
04/07/2025
CR202502766
Mounting Screw Snapped During Reinstallation on FCV
'A' RVDT
04/13/2025
Corrective Action
Documents
CR202503227
Abnormal Movement of Flow Control Valve 'A'
04/29/2025
Engineering
Changes
251067-001
Reactor Recirculation System Discharge Block Valve
(1B33F0067A) Actuator Motor Replacement
Procedures
SVI-B33T1158B
Reactor Recirculation Flow Control Valve 1B33F060B
Functional Test
CR202503401
Turbine Mechanical Overspeed Indicated Test Malfunction 05/03/2025
Corrective Action
Documents
CR202503449
Main Transformer 'C' Cooler 1 and 4 Trouble
05/06/2025
20080220-00006
TDUN 251094-001001
2080151-00399
Turbine Cntrl Emergency Trip Sys
2080220-00006
Power Transformers
R
Drawings
2090220-00020
Temporary Drawing Update Notice 251094-001003
Engineering
Changes
ECP 250194
Temporary Power Set up for the F1A12 Transformer
05/08/2025
ARI-
S11S001C0001A5
Cooler No. 1 Trouble
Procedures
ARI-
S11S001C0001A7
Cooler No. 4 Trouble
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PAP1925
Shutdown Defense in Depth Assessment and
Management
200517736
Cable Diagnostic Withstand Tests
06/16/2025
200872933
Deenergized/Energized Motor Analysis-LR
06/16/2025
Work Orders
200933745
Inspect/Tighten ESW 'A' Pump Packing
06/16/2025
CR202305197
Div. 2 DG Exhaust Louver is Dusty and Needs Cleaned
06/29/2023
CR202406674
Div. 2 Diesel exhaust Damper Screen Dirty
08/19/2024
CR202503056
Offgas Pretreat Sample Selector Panel Doesn't Have
Power
06/09/2025
CR202503056
Offgas Pretreat Sample Selector Panel Doesn't Have
Power
04/22/2025
Corrective Action
Documents
CR202503793
Div 2 Diesel Generator Exhaust Screen Need Cleaned
05/19/2025
Miscellaneous
Perry Open Mode Hold and PCR Forms Mode Restraint
List
04/08/2025
Procedures
ICI-C-C513
Intermediate Range Monitoring (IRM) Voltage Preamplifier
Calibration
Work Orders
200922062
RPS Power Transfer Switch Replacement
04/17/2025
CR202409654
Low Pressure Core Spray Waterleg Pump Oil Seals
Leaking
2/18/2024
CR202501189
Drywell Radiation Monitor Inboard Suction Isolation Failed
Stroke Time Close Per SVI-D17T2001
2/23/2025
CR202501917
Ability to Complete Cable Testing on LH2A is Challenged
Due to Inprocessing and Accessing Issues
03/19/2025
CR202502009
Outboard Main Steam Isolation Valve 'A' Stroke Time Was
Fast for SVI-B21T2001
03/22/2025
CR202502094
Pre Fab Does Not Match AsFound Condition for LPCS
Waterleg Pump to RHR A Discharge Check Valve
03/25/2025
CR202502192
Phasing Checks Failed on LH2A
03/27/2025
CR202502212
RHR Shutdown Cooling Suction Line Min Path Leakage
Limit Exceeded
03/27/2025
CR202502265
Loss of L20 Bus During Breaker Trip Check Testing
03/29/2025
CR202502338
Plant Computer Failover During Div 1 Diesel Test
03/31/2025
Corrective Action
Documents
CR202502339
1R20 SVI-R43T7000A Division 1 Integrated Test Data
04/01/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR202502655
Main Steam Line 'A' Outboard MSIV AsFound Inspection
Results
04/10/2025
Corrective Action
Documents
Resulting from
Inspection
CR202501985
NRC Identified: Methods for Crediting Systems for
Shutdown Defense in Depth Not Clear
03/21/2025
Engineering
Changes
ECP 210194-002
PDUN 210194-001002
Engineering
Evaluations
601486502
MSIV Spring Cap, Guide Lug Interference
04/11/2025
FTI-F0038
Hydrostatic Pump Testing Instruction
GEI0001
Performing Insulation Resistance Checks
ICI-B120001
ITT NH90 Series Milliampere Proportional/OnOff
Hydramotor Actuator Calibration
ICI-C513
IRM Voltage Preamplifier Calibration
ISI-B21T13001
Reactor Coolant System Leakage Pressure Test
PMI0061
Overhaul of NH95 Hydramotors
PTI-P54P3200
Fire Suppression Valve Cycle and Position Switch
Functional Test
03/25/2025
SOI-G33
Reactor Water Cleanup System
SVI-B21T2001
MSIV Full Stroke Operability Test
SVI-B21T9000
Type C Local Rate Test of 1B21 MSL Penetration (P122,
P124, P415 and P416)
SVI-B21T9000
Type 'C' Local leak Rate Test of 1B21 MSL Penetrations
(P122, P124, P415, and P416)
SVI-C71T0038E
MSIV 1B21F028A Closure Channel Calibration for
1C71N702A and 1C71N703A
SVI-E12T2200
RHR Shutdown Cooling Suction Isolation Valve
Operability Test
SVI-E12T2210
Leak Rate Test for RHR to FDW Injection Valves
1E12F050A and 1E12F053A
Procedures
SVI-E21T2004
LPCS and RHR 'A' Waterleg Pump and Associated Valve
Cold Shutdown Operability Test
03/29/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SVI-E21T2200
Low Pressure Core Spray Isolation Valve Leak Rate Test
SVI-E22T1319
Diesel Generator Start and Load Division 3
SVI-E51T9422
Type C Local Leak Rate Test of 1E51 Penetration P422
SVI-E51T9422
Type C Local Rate Test of 1E51 Penetration P422
SVI-P53T9024
Drywell Airlock in Between Seals Test
SVI-R43T7000A
Division 1 ECCS Integrated Test
04/01/2025
SVI-T23T1022
Drywell Airlock Interlock Verification
200242803
MSIV-CPLO Rebuild OB MSIV 'A'
04/13/2025
200242803
MSIV-CPLO Rebuild OB MSIV 'A'
04/25/2025
200679637
1E12F0084A Dresser Valve Replacement
04/05/2025
200859641
Perry S2 Bus Backup Bus Diff-U2S/U - ECP 210194-002
04/10/2025
200903818
Replace High Voltage XFMR Fuse
03/27/2025
200906321
Static MOV Test (ASME OM Code) & PM Ins
03/29/2025
200906342
Gen. Insp. / Double Complete Test 1PUY-T XFMR A0,
B0, C0
04/23/2025
200909389
SVI-B21T2201 MSIV Full Strike OPER PiCal
03/22/2025
200910660
SVI-C71T0038E OTBD MSIV Closure CH 'A'
04/16/2025
200911995
SVI-B21T900 1B21 MSL Penetration LLRT
03/24/2025
200946729
Blast Shield Door to be Opened Closed in the Normal
Course. Defeat/Restore DW Interlocks on DW Airlock
Hatch. Of IOI17, Drywell Entry
04/18/2025
200967423
Replace Hydramotor 1D17F0071B
04/12/2025
Work Orders
SVI-D17T9201
Type C Local Leak Rate of 1D17 Penetration P201
Miscellaneous
Perry ERO Integrated Drill Scenario Guide
06/11/2025
EMA 0083 7/22
State of Ohio Supplemental Action Default Actions - PNPP
06/11/2025
NOP-LP550309
Perry Emergency Notification Cover Sheet
Procedures
NOP-LP550312
Industry Event Notification
MS05 Performance
Indicator Data
Safety System Functional Failures
03/31/2025
MS06 Performance
Indicator Data
Emergency AC Power Systems
03/31/2025
71151
Miscellaneous
MS07 Performance
Indicator Data
High Pressure Injection Systems
03/31/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR202408053
Container in the Outside Radiological Controlled Area
Leaked Radioactive Water
10/14/2024
Corrective Action
Documents
CR202504315
Fire in Warehouse #6
06/11/2025