IR 05000440/2023011
| ML23328A018 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/28/2023 |
| From: | Billy Dickson NRC/RGN-III/DORS/RPB2 |
| To: | Penfield R Energy Harbor Nuclear Corp |
| References | |
| IR 2023011 | |
| Download: ML23328A018 (1) | |
Text
SUBJECT:
PERRY NUCLEAR POWER PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000440/2023011
Dear Rod Penfield:
On October 26, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Perry Nuclear Power Plant and 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.
The NRC inspection team reviewed the stations problem identification and resolution program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for problem identification and resolution programs.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
November 28, 2023 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, Billy C. Dickson, Jr., 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-2023-011-0038
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Perry Nuclear Power Plant
Location:
Perry, OH
Inspection Dates:
October 09, 2023 to October 26, 2023
Inspectors:
J. Beavers, Senior Resident Inspector
B. Jose, Senior Reactor Inspector
D. Melendez-Colon, Reactor Inspector
R. Ng, Senior Project Engineer
Approved By:
Billy C. Dickson, Jr., 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 a biennial problem identification and resolution 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
None.
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 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)
- (1) The team performed a biennial assessment of the effectiveness of the licensees Problem Identification and Resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Problem Identification and Resolution Effectiveness: The teams assessed the effectiveness of the licensees Problem Identification and Resolution program in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of chillers related issues. The team also reviewed the corrective actions for selected NRC non-cited violations and findings.
- Operating Experience: The team assessed the effectiveness of the licensees processes for use of operating experience.
- Self-Assessments and Audits: The team assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
- Safety Conscious Work Environment: The team assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Assessment of the Corrective Action Program Based on the samples reviewed, the team concluded that the licensee's implementation of the Corrective Action Program (CAP) was generally effective and supported nuclear safety.
Effectiveness of Problem Identification:
Based on the samples reviewed, the team determined that the licensee continued to identify issues at a low threshold and appropriately entered these issues into the CAP. The team also determined that the licensee usually entered problems into the CAP promptly and accurately.
The team noted that issues were being identified by all levels of the organization and with varying degrees of safety significance. External organizations, including the NRC identified some deficiencies, and the licensee subsequently entered these issues into the CAP for resolution. The licensee also utilized several CAP support processes to identify problems, including the self-assessment and audit processes and the Operating Experience (OE)
Program. For example, the licensee performed departmental self-assessments and Nuclear Oversight audits to identify issues in station processes. The licensee entered the identified deficiencies and improvement opportunities into the CAP for resolution. Similarly, the licensee screened issues from the NRC and industry OE programs and entered them into the CAP when they applied to the station.
The team determined that the licensee was generally effective at trending low-level issues and taking appropriate corrective actions to prevent more significant problems from developing. In addition, the licensee used the CAP to document instances in which previous corrective actions were ineffective or were inappropriately closed.
The team performed a 5-year review of chiller-related issues. Specifically, the team focused on the safety-related chillers of the control complex chilled water system. The team performed system walk-downs and evaluated condition reports for recurring or age-related issues as part of the review. Overall, the inspectors determined that the licensee effectively managed problems associated with chillers and identified and entered deficiencies and concerns into the CAP at a low threshold. Corrective actions were adequate and timely, commensurate with their safety significance. The team did not identify any deficiencies or trends in this area.
Effectiveness of Prioritization and Evaluation of Issues:
Based on the samples reviewed, the team determined that licensee performance was generally effective at prioritizing and evaluating issues commensurate with the safety significance of the identified problem. Once the licensee identified a degraded or non-conforming issue, the CAP process effectively directed equipment operability or functionality reviews. The licensee used a multi-discipline team, the Management Review Board, consisting of department directors and managers, to verify that the condition report categorization, evaluation method selection, and other actions adequately addressed the scope and significance of the documented issue. Upon completing the evaluation or action, the Corrective Action Review Board, a multi-discipline team of managers and directors, reviewed those actions to ensure they met the CAP requirements.
During the Management Review Board and Corrective Action Review Board meetings, the team observed that licensee staff were generally thorough and intrusive in reviewing and screening issues. The team also observed healthy dialogues and good interactions among the members of the respective groups. The members came prepared and challenged each other on the disposition of the identified conditions. Actions were prioritized based on the safety significance of the issues. The team did not identify any deficiencies or trends in this area.
Effectiveness of Corrective Actions:
Based on the samples reviewed, the team determined that the licensee was generally effective in corrective action implementation. In general, corrective actions for deficiencies that were safety significant were implemented in a timely manner. Problems requiring the performance of a root cause evaluation or other causal evaluation methodologies were resolved following CAP requirements. The team sampled assignments associated with violations identified by the NRC previously and with licensee event reports. The team determined that the corrective actions sampled were generally timely and commensurate with the safety significance of the problem.
The team also reviewed the licensees implementation of the Maintenance Rule Program.
Specifically, the team reviewed Maintenance Rule Program procedures and conditions reports. The team selected one of the systems classified as Maintenance Rule (a)(1), reactor water cleanup system (RWCU), for an in-depth review. The team reviewed documentation for scoping the system into the Maintenance Rule program, the systems risk significance determination, performance criteria selection, Maintenance Rule (a)(1) evaluations, action plans, and goals. The team also reviewed the most recent Maintenance Rule (a)(3) periodic assessment. The team determined that the licensee effectively implemented the Maintenance Rule Program with this system. The licensee has identified issues with the system, entered those issues into the CAP, and addressed those issues per the (a)(1) action plan under the CAP.
Assessment 71152B Use of Operating Experience Based on the samples reviewed, the team determined that the licensee's performance in using Operating Experience (OE) was generally effective. The licensee screened industry and NRC OE information for applicability to the station. When applicable, the licensee wrote condition reports and developed and implemented actions to prevent similar issues. The licensee communicated OE lessons learned and incorporated these lessons learned into plant operations. The team observed the licensee using OE information in daily activities, such as pre-job briefs, issue reviews, and investigations. The licensee also highlighted selected issues at other Energy Harbor sites in daily meetings or activities.
The team noted that from a licensees self-assessment performed for this PI&R inspection, not all Part 21s listed for the years 2021, 2022, and 2023 were screened in a timely manner. Each department generally reviewed operating experience, including Part 21s from Industry and NRC, for applicability to Perry. Based on this self-assessment finding, the licensee generated action items to ensure the future timeliness of Part 21 screening. The team reviewed the licensee's planned actions and the Part 21s in question and did not identify any concern of more than minor significance.
Assessment 71152B Self-Assessments and Audits Based on the samples reviewed, the team determined that the licensee's performance of self-assessments and audits was generally effective. The licensee performed departmental self-assessments and Quality Assurance audits throughout the organization periodically.
These self-assessments and audits were generally effective at identifying issues and enhancement opportunities at an appropriate threshold. The self-assessments and audits reviewed by the team were thorough and intrusive in assessing the underlying topics. These self-assessments and audits identified issues that the station did not previously recognized.
In general, any identified issues were captured, and actions were taken to address in the CAP. The team did not identify any concerns in this area.
Assessment 71152B Safety Conscious Work Environment The team reviewed the Perry 2022 Safety Conscious Work Environment (SCWE) survey result for this inspection. The team noted that the survey results revealed some negative responses regarding the Employee Concerns Program (ECP) and departmental SCWE issues. As a result, the team reviewed licensee actions to address the negative survey results. The team also interviewed a representative cross-section of licensee personnel, including individual contributors and supervisors from various departments and long-term contractors at the site. The team also interviewed the ECP manager and reviewed selected ECP case files. A total of 27 licensee personnel were interviewed during this inspection.
Based on the individual interviews and a review of the licensee's actions, the team determined that licensee staff could raise nuclear safety and safeguards issues through multiple channels, including ECP, without fear of retaliation and that the CAP effectively addresses quality issues. Therefore, the team found no evidence of challenges to the SCWE at Perry.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 26, 2023, the team presented the biennial problem identification and resolution inspection results to Rod Penfield and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2015-08036
PFA Needed for Site Flooding Issues
06/08/2015
CR-2018-00698
Need to Determine the Classification and Requirements of
the Door in the MB100 Lube Oil Issue Room
01/26/2018
CR-2018-05939
NRC EQ DBAI: Accounting for Heat Rise in EQ Component
Evaluations
06/28/2018
CR-2019-00401
Spent Fuel Pool Level Indicator 1X13R0001 Out of Band
01/15/2019
CR-2020-00830
RFB Pump B Discharge Check Valve Leak Sealant Clamp
TCC-1-N27-LR-001 Not Scoped in 1R18
2/03/2020
CR-2021-00824
M&TE Out of Tolerance Resulted in Exceeding Allowable
Band
2/09/2021
CR-2021-01650
Roll-up CR for Loss of Both RWCU Pumps
03/07/2021
CR-2021-01763
MS-C-21-03-30: FINDING: Ineffective Corrective Actions:
Failure to Meet the Corrective Action Requirements of
CFR 72.172 on Documenting Equipment Failures during
the Spent Fuel Dry Storage Campaign #4
03/12/2021
CR-2021-02894
Reactor Water Cleanup System (RWCU) Containment
Isolation Valves (Penetration (P132)) Issues
04/14/2021
CR-2021-05408
21 DBAI POV Inspection: RCIC Steam Supply Isolation
Valves Questionable Calculation Justification
07/15/2021
CR-2021-05435
Addition - 2021 DBAI POV Inspection: JOG Classification of
RCIC Steam Supply Isolation Valves
07/16/2021
CR-2021-07175
Control Room Habitability Assessment: Deficiency Exists in
Tracking Control Room Boundary Deficiencies as Potential
Limiting Conditions for Operation
09/24/2021
CR-2021-07423
NRC NCV - Failure to Establish a Program to Ensure Motor
Operated Valves Continue to be Capable of Performing Their
Design Basis Safety Functions
10/05/2021
CR-2021-07479
CCCW Chiller C High Voltage Power Lead Found Degraded
10/07/2021
CR-2021-07840
Unit 2 Safety Bus EH21 Does Not Appear to Meet Class 1E
Requirements
10/18/2021
Corrective Action
Documents
CR-2021-07840
Unit 2 Safety Bus EH21 Does Not Appear to Meet Class 1E
Requirements
10/18/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-08059
Drywell Unidentified Leak Rate Changed Following Drywell
Ventilation Shift
10/24/2021
CR-2021-08550
Wear Damage on Internal Parts of Filter Dryer for Control
Complex Chiller 'C'
11/09/2021
CR-2021-08630
MS-C-21-11-24: Emergency Preparedness Inventory
Discrepancy
11/11/2021
CR-2021-08632
MS-C-21-11-24: Procedure Issues at the EOF, TSC,
11/11/2021
CR-2021-09019
ENS Phone Challenges
11/27/2021
CR-2021-09050
Measuring and Test Equipment (M&TE) Not Available for
Surveillance Testing (SVI-R45-T2003)
11/28/2021
CR-2021-09065
Control Complex Chilled Water Chiller C Temperature
Sensor Failures
11/29/2021
CR-2021-09379
Slow Steady Rise in Reactor Recirc A Pump Outer Seal
Pressure
2/11/2021
CR-2021-09454
One Radiation Protection Technician Did Not Respond to the
Unannounced Call-In Test in a Timely Manner
2/14/2021
CR-2021-09462
Changes Made by ECP Were Not Incorporated into
Calculation M25-000
2/14/2021
CR-2021-09536
Compressor Discharge Temperature Sensor Part
Interchangeability Evaluation (PIE) Did Not Identify Change
to Wire Sleeve Effecting Installation
2/16/2021
CR-2022-00376
Impact on Perry from the DB NRC NCV for Failure to
Analyze NIX System and Identify the System as a CDA
01/18/2022
CR-2022-00764
Debris Captured during Condensate Storage Cleaning
2/01/2022
CR-2022-00764
Debris Captured during Condensate Storage Cleaning
07/16/2021
CR-2022-00784
RWCU Pump A Confirmed Thermal Neck Failure
2/02/2022
CR-2022-04231
Relay Contacts 3 to 5 Indeterminate for Relay 0P47Q7024
05/19/2022
CR-2022-04267
RHR Pump B Seal Replacement Scheduling Decision
05/20/2022
CR-2022-04425
Emergency Notification System Phone in the Control Room
Not Functioning Properly
05/26/2022
CR-2022-04679
Work Order 200860078 to Inspect RWCU Return Header
Outboard Isolation Valve Not to be Performed as Required
by CA-2021-02894-001
06/07/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2022-05107
LPCS Minimum Flow Valve Blew 2 Main Line Fuses
06/24/2022
CR-2022-05808
Configuration Control Committee: Identified Development of
a Trend Relative to Components Installed outside of
Approved Engineering Processes
07/26/2022
CR-2022-05861
Residual Heat Removal Pump B to Feedwater Line Flush
Check Valve Leaking
07/22/2022
CR-2022-06077
Rise in Drywell Unidentified Leakage
08/07/2022
CR-2022-07267
Control Complex Chiller C (P47C) Chiller Oil Level High
09/26/2022
CR-2022-07297
ERO Drill - Unplanned Controller Injects
09/28/2022
CR-2022-07396
Low Oil Level - Control Complex Chiller C
10/02/2022
CR-2022-07407
Rise in Unidentified RCS Leakage
10/03/2022
CR-2022-07485
Drywell Unidentified Leakage Classified as RED (>= 1.0
GPM) per PYBP-SITE-0029
10/06/2022
CR-2022-08252
Contamination Found in Clean Area During Walkdown in
HB60002 - LHRA due to Steam Leak
10/31/2022
CR-2022-08498
Reactor Recirculation Pump A Seal Leakage
11/07/2022
CR-2022-08733
Installed Time-Delay Relays Discovered to Certain Digital
Components
07/25/2022
CR-2022-09009
Control Complex Chiller C - Oil High
11/24/2022
CR-2023-00877
23 Pre-NRC Comprehensive Engineering Team Inspection
(CETI) Inspection: Non-Timely Follow-Up Action Resolution
to OE-2021-0208-1
2/08/2023
CR-2023-00893
During the Fix It Now (FIN) Minor Work Screening Process, a
Conditional Single Point Vulnerability Was Missed
2/08/2023
CR-2023-01054
23 Pre-NRC CETI Self-Assessment: Diesel Generator
SVIs for Voltage and Frequency Do Not Account for
Measurement Uncertainty
2/15/2023
CR-2023-01158
Elevation: Events with Significant Plant Impact within the
Past Six Months
2/20/2023
CR-2023-01409
Improvement Opportunities with Scaffold Conditions
2/28/2023
CR-2023-01744
Storage Level B Areas Not Monitored by Calibrated
Temperature Sensing Devices
03/09/2023
CR-2023-01994
Faulty Accumulat3ed Dose Alarm Received by work
03/15/2023
CR-2023-02047
1R19 LLRT: Main Steam Line Penetrations Leakage
03/17/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Exceeds SVI-B21-T9000 Step 5.3.4 Acceptance Criterion
CR-2023-02100
Individual Received Un-Briefed Dose Rate Alarm
03/19/2023
CR-2023-03180
Irregular Calibration Factor on Dosimeters Causes Faulty
Alarms
04/18/2023
CR-2023-03677
Possible Degrading Trend of Control Complex Chilled Water
Train C
05/01/2023
CR-2023-03720
Reactor Water Clean-Up Roll-Up CR
05/02/2023
CR-2023-03943
Armed Security Officer Outside of Their Area of
Responsibility
05/10/2023
CR-2023-03997
Control Complex Chilled Water "C" Chiller Trip
05/12/2023
CR-2023-04447
Loss of Network Resulting in Loss of NRC ENS Line and
05/30/2023
CR-2023-04821
Drywell Identified Leakage Step Change Improvement
06/15/2023
CR-2023-04907
Faulty Self-Reading Dosimetry
06/19/2023
CR-2023-05010
Loss of Network Resulting in Loss of NRC ENS Line and
06/23/2023
CR-2023-05021
Yokogawa Recorder Found With "Media not Inserted"
Message on Screen on Hydrogen Recombiner
06/23/2023
CR-2023-05319
Emergency Notification System Phone (Red Phone in
Control Room) is Not Working
07/05/2023
CR-2023-05433
Motor Control Center Drawing Updates not Performed
07/11/2023
CR-2023-05433
Motor Control Center (MCC) Overloads Drawing Updates Not
Performed for Overload Relays
07/11/2023
CR-2023-05467
Emergency Telecommunication System Phones Inoperable
07/12/2023
CR-2023-05801
M&TE Probe Missing
07/25/2023
CR-2023-05901
MS-C-23-07-08: Condition Report Categories Incorrectly
Assigned for M&TE Condition Report and Inadequate Details
in Condition Report to Fully Identify the Issue
07/28/2023
CR-2023-06088
NRC Minor Violation: Non-Conforming Condition due to
Incorrect Gasket Installation in the Standby Liquid Control
(SLC) System
08/04/2023
CR-2023-06345
DC Bus ED-1-A Ground Fault Alarm
08/15/2023
CR-2023-06399
Fire Door IB-108 Will Not Latch
08/17/2023
CR-2023-06607
Degrading Trend in Fuel Pool Cooling and Clean Up System
08/24/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2023-06649
Grid Disturbance Observed During Severe Thunderstorm
08/25/2023
CR-2023-07969
Illuminate Implementation Delay
10/23/2023
CR-2023-07969
Illuminate Implementation Delay
10/23/2023
CR-2023-07676
23 PI&R Inspection: Incorrect Document Provided to 2023
NRC Inspection Team
10/11/2023
CR-2023-07945
23 PI&R Inspection. CR-2023-03180 Was Incorrectly
Classified as NC Instead of AF
10/23/2023
CR-2023-07964
23 PI&R Inspection: CA-2022-05808-008 Identified Closed
Without Objective Evidence
10/23/2023
Corrective Action
Documents
Resulting from
Inspection
CR-2023-07994
23 NRC PI&R Inspection: CR-2021-09379 Was Incorrectly
Classified as An NC Instead of n AC
10/24/2023
Drawings
40-0425-00004
Gate Valve Assembly 1E21F0011
A
EER 601214678
Develop TCC Package to Replace TMod
06/11/2019
OE-2021-0105-7-
Berried Cast Iron Fire Protection Piping
09/22/2023
OE-2021-0471-1
Nine Mile Point; Safety-Related Service Water Discharge
Motor Operated Valve (MOV) Failed to Open
06/30/2022
OE-2022-0276-1
Limerick Reactor Pressure Rise Caused by Turbine Control
Valve Position Oscillation
2/16/2023
OE-2022-0361-3
RIS-2022-02; Operational Leakage
04/10/2023
OE-2023-0022-1
Watts Bar Hotwell Pump Upper Motor Bearing Failure
08/16/2023
OE-2023-0032-1
River Bend High Pressure Core Spray (HPCS) Inoperable
due to Transformer Feeder Malfunction
07/25/2023
Engineering
Evaluations
OE-2023-0091-1
IN-2023-01; Risk Insights from High Energy Arcing Faults
08/05/2023
Maintenance Rule System Basis Document - System G33
NIX Upgrade Project Management Plan
Perry 2022 SCWE Survey
09/2022
CR-2022-06020
Maintenance Rule (a)(1) Evaluation Form for System
PY-G33
11/29/2022
CR-2022-08509
Manual Trip of Main Turbine During Startup
11/07/2022
CR-2023-03747
10CFR Part 21 Communications: Failure of the Control Rod
Drive Collet Retainer Tube/Outer Tube Weld
05/03/2023
Miscellaneous
CR-2023-06100
10CFR Part 21 Notification: P21-08032023-IN from Paragon
Energy Services Regarding Safety Contactors Failing in the
08/04/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Energized Position
CR-2023-06141
Emergency Response Organization Notification System
(ERONS) Weekly Notification Test Performed Incorrectly
08/07/2023
CR-2023-06215
Automatic Reactor SCRAM and MSIV Closure Following
RPS Bus Shift from ALT to NORM B
08/10/2023
CR-2023-06871
General Electric Hitachi (GEH) Issued Non-Reportable
10CFR Part 21 Impacting Control Blade Lifetime Limits
09/05/2023
MS-C-21-11-24
Quality Assurance Multi-Site Audit of Emergency
Preparedness
10/22/2021
MS-C-22-03-01
Quality Assurance Multi-Site Audit of Operations
03/07/2022
MS-C-22-11-24
Quality Assurance Multi-Site Audit of Emergency
Preparedness
11/16/2022
MS-C-23-01-13
Quality Assurance Audit Report Design Control/Engineering
Programs/ASME
2/21/2023
MS-C-23-02-16
Quality Assurance Audit Report Procurement Program
03/23/2023
QFO-2021-0015
21 Maintenance and Work Management Audit
10/07/2021
QFO-2022-0003
22 Maintenance and Work Management Audit
07/01/2022
QFO-2023-0003
Measuring and Test Equipment (M&TE) Audit, 2023
07/21/2023
QFO-2023-0006
Cyber Security Audit, 2023
07/21/2023
NOBP-ER-3003
System Performance Monitoring Program
NOP-ER-3004
NOP-LP-2001
Corrective Action Program
NOP-OP-4205
Dose Assessment
Procedures
PYBP-PES-0001
Maintenance Rule Reference Guide
Periodic Assessment of the Maintenance Rule Program
Perry Nuclear Power Plant Cycle 19 April 09, 2021 through
April 20, 2023
08/24/2023
ATA-2021-12905
Pre-NRC In-Plant Airborne and Occupational Dose
Assessment
2/17/2021
ATA-2022-2193
PNPP Site Protection 2022 Safety Assessment
09/19/2022
ATA-2022-2379
Radiation Waste Shipping and Processing Assessment
06/17/2022
Self-Assessments
ATA-2022-7625
PY Equipment Performance Testing and Maintenance
Inspection Self-Assessment (Security)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ATA-2023-0594
Perry 2022 Annual Self-Assessment on Clearance Process,
Procedures and Practices
2/23/2023
ATA-2023-10673
Pre-NRC Inspection on Problem Identification and Resolution
08/22/2023
ATA-2023-12406
23 PY Pre-NRC EP Self-Assessment Plan
08/15/2023
ATL-2020-0084-
ATA-31
Perform an Assessment on the Plant Health Committee
2/28/2021
ATL-2021-0401-
ATA-55
Ops Fundamentals Self-Assessment
10/01/2021
ATL-2021-0768-
ATA-29
Work Order Closure Effectiveness Review
09/06/2023
CR-2021-04919-
ATA-04
Past Reportability Review Assessment
07/11/2022
CR-2023-01022
23 Pre-NRC Comprehensive Engineering Team Inspection
(CETI) Self-Assessment; Follow-Up to Previous Part 21
Notifications not yet Addressed
2/14/2023
CR-2023-05964
Receipt of Vendor Technical Information is Not Always
Tracked Per NOP-CC-1003
08/01/2023
200776963
Calibrate Meter 1X13R001
2/22/2019
200785743
Rebuild/Replace Mechanical Seal Reactor Recirc Pump "A"
01/19/2023
Work Orders
200887747
T/S Repair Valve Replace Blown Fuses - LPCS Pump
Min-Flow Valve
08/12/2022