IR 05000440/2020003
| ML20318A046 | |
| Person / Time | |
|---|---|
| Site: | Perry, 07200069  |
| Issue date: | 11/12/2020 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Payne F Energy Harbor Nuclear Corp |
| References | |
| IR 2020001, IR 2020003 | |
| Download: ML20318A046 (20) | |
Text
November 12, 2020
SUBJECT:
PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000440/2020003 AND 07200069/2020001
Dear Mr. Payne:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Perry Nuclear Power Plant. On October 22, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No 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,
/RA/
Billy C. Dickson, Jr, Chief Branch 2 Division of Reactor Projects
Docket Nos. 05000440; 07200069 License No. NPF-58
Enclosure:
As stated
Inspection Report
Docket Number:
05000440; 07200069
License Number:
Report Number:
05000440/2020003; 07200069/2020001
Enterprise Identifier: I-2020-003-0032
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Perry Nuclear Power Plant
Location:
Perry, OH
Inspection Dates:
July 01, 2020 to September 30, 2020
Inspectors:
S. Bell, Health Physicist
R. Edwards, Senior Health Physicist
N. Fields, Health Physicist
J. Nance, Operations Engineer
T. Ospino, Resident Inspector
J. Steffes, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr, Chief
Branch 2
Division of Reactor Projects
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
None.
PLANT STATUS
The plant began the inspection period at rated thermal power. On September 12, 2020, reactor power was lowered to 58 percent to perform a rod sequence exchange. Operators returned the unit to rated thermal power on September 13, 2020. The unit remained at, or near, rated thermal power for the remainder of the inspection period except on the occasions where operators reduced power to maintain condensate demineralizer outlet temperature and high condenser circulating water outlet temperature at or below their respective upper limits due to environmental conditions. The power reductions varied between 1 and 16 percent of rated thermal power and lasted from a few hours to several days.
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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities, and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
- (1) Residual heat removal (RHR) system C on July 30, 2020
- (2) Division 1 diesel generator on August 28, 2020
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 downpower for, and during, rod sequence exchange on September 12, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the simulator on August 31, 2020
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) Fire protection system following excessive vibrations observed during motor fire pump functionality test on September 4, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Emergent work and risk assessment associated with the plant process computer upgrade activities between July 1 to August 7, 2020
- (2) Emergent work and risk assessment associated with the overspeed trip work on the high pressure core spray (HPCS) system on August 8, 2020
- (3) Emergent work and risk assessment associated with the unplanned inoperability of the standby liquid control (SLC) system on August 21, 2020
- (4) Emergent work and risk assessment associated with reactor water cleanup system A on September 18 to 20, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) HPCS ESW 1P45F0552 check valve prompt operability determination on July 13, 2020
- (2) SLC tank high level alarm during performance of standby liquid transfer system surveillance on August 20, 2020 3)
Local power range monitor operability challenged following gain adjustments that could not be validated due to plant process computer communication issues on July 21 to 23, 2020
- (4) Review of compensatory measures associated with the unexpected seismic system non-functionality on August 24 to 26, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Unit 2 air compressor electrical breaker, H2210, functionality following refurbishment on July 20, 2020
- (2) HPCS system following the replacement of the emergency service water heat exchanger relief valve on August 8, 2020
- (3) Division 3 diesel generator system performance following potentiometer R3 replacement on August 8, 2020
- (4) Axial power range monitor D channel calibration of 1C51-K605D following relay replacement on August 10, 2020
- (5) Division 1 diesel generator system operability test following ventilation damper motor replacement on August 21, 2020
- (6) SVI-C41-T1026, "Standby Liquid Control Boron Concentration," following chemical addition to restore SLC system operability on August 27, 2020
- (7) Unit 2 air compressor test following the replacement of two Potter & Brumfield time delay relays on September 22, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Remote shutdown control panel reactor core isolation cooling system surveillance on July 21, 2020
- (2) SVI-R44-T2002, "Division 2 Diesel Generator Starting Air SCV and FCV Operability Test" on July 27, 2020
- (3) SVI-C41-T2001B, "Standby Liquid Control B Pump and Valve Operability Test" on July 31, 2020
- (4) A RHR system operability test on September 20, 2020
- (5) SVI-C51-T0027-A, "APRM A Channel Functional for 1C51-K6005A" on September 22, 2020
- (6) B recirculating water pump hydraulic unit 1 functionality test following filter replacement on September 24, 2020
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) C RHR system operability test on July 30, 2020
- (2) HPCS pump discharge pressure surveillance on August 2, 2020
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Drywell floor drain sump surveillance on August 24, 2020
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Inspectors observed and evaluated licensee performance during the emergency response organization integrated drill on August 12 to 13,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Fuel Handling Building Ventilation System
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Maintenance Rebuild Room 599' Intermediate Building
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (3 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Liquid Radwaste System - Auxiliary Building East 620 (including the Radiation Monitor) and the Radwaste Building 602' (including the Discharge Flow Control Valves)
- (2) Unit One Plant Vent (including associated Radiation Monitor and sampling lines located in the Intermediate Building 682)
- (3) Offgas Gaseous Effluent System (including the associated Radiation Monitor and sampling lines from the Turbine Building 620' to discharge header)
Sampling and Analysis (IP Section 03.02) (3 Samples)
- (1) Inspectors evaluated the compensatory sample program
- (2) Inspectors evaluated the sampling and sample analysis of the U1 Plant Vent
- (3) Inspectors evaluated the sampling and sample analysis of the Unit 2 Turbine Power Complex Sump
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) January 2020 Liquid and Gaseous Effluent Release Data
- (2) February 2020 Liquid and Gaseous Effluent Release Data
Abnormal Discharges (IP Section 03.04) (1 Sample)
The inspectors evaluated the following abnormal discharges:
- (1) In-leakage into the Nuclear Closed Cooling (NCC) system in 2018-2019
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, 2019-June 30, 2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) Unit 1 (July 1, 2019-June 30, 2020)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) Unit 1 (July 1, 2019-June 30, 2020)
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) Unit 1 (07/01/2019-06/30/2020)
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants
- (1) The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loading from August 17 to August 21, 2020. Specifically, the inspector observed the following activities:
- Radiological contamination survey of the annulus between the transfer cask (HI-TRAC) and the Multi-Purpose Canister (MPC) and removing the annulus seal on August 17
- Hydrostatic test of the lid-to-shell weld and the post-hydro visual and dye penetrant examinations of the lid-to-shell weld on August 18
- Vacuum drying and backfill evolutions on August 18 and 19
- Vent and drain port cover plate welding on August 19
- Transfer of the MPC from the HI-TRAC to the storage cask (HI-STORM) and transport of the HI-STORM from the fuel handling building on August 20
The inspector performed a walkdown of the ISFSI pad, including independent radiation surveys, and a walkdown of the ISFSI haul path on August 20.
The inspectors evaluated the following:
- Spent fuel selection for the 5 casks in the loading campaign
- Selected condition reports written since November 2018
- Selected 10 CFR 72.48 screenings performed since November 2018
- Update of the Perry 10 CFR 72.212 Evaluation Report to Revision
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 31, 2020, the inspectors presented the radiation protection baseline inspection results to Mr. F. Payne, Site Vice President, and other members of the licensee staff.
- On August 21, 2020, the inspectors presented the independent spent fuel storage installation cask loading inspection results to Mr. F. Payne, Site Vice President, and other members of the licensee staff.
- On October 22, 2020, the inspectors presented the integrated inspection results to Mr. F. Payne, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60855.1
ALARA Plans
200316
Load Spent Fuel into HI-STORM's # 919/920/921/922/923
Calculations
Assemblies and Decay Heat for First Spent Fuel Dry
Storage Campaign
09/17/2010
Corrective Action
Documents
Selected Condition Reports
11/01/2018 to
08/21/2020
CR-2013-04223
MS-C-13-03-30: Spent Fuel Dry Storage FSAR Contains
Conflicting Direction
03/22/2013
CR-2020-04224
Auxiliary Hook Reeving Questioned
05/13/2020
CR-2020-06009
Dry Cask Storage - MPC #496 Drain Tube Length Short
07/28/2020
CR-2020-06816
MPC #500 Drain Tube Came Into Contact with HI-TRAC
08/31/2020
FCR30781002-
R1,
FCR30781007,
FCR30781009
Holtec Field Condition Reports
07/27/2020,
08/04/2020,
08/11/2020
Corrective Action
Documents
Resulting from
Inspection
CR-2020-06507
20 NRC ISFSI Inspection: PMI-0031, Fuel Handling
Building Crane Preventative Maintenance Errors
08/18/2020
Engineering
Changes
2.48 Evaluation
No. 1298
ECO 5014-266R1
2.48 Evaluation
No. 1353
SMDR-1021-2785
2.48 Screen No.
20-01017
Revision 10 to Perry 10 CFR 72.212 Evaluation Report
ECO 5014-266
Decrease the Local Temperature Limit Under Short-Term,
Off-Normal, and Accident Conditions from 650F to 572F
Engineering
Evaluations
Perry Nuclear Power Plant 10 CFR 72.212 Evaluations
Report
SMDR 1021-2785 MPC-68 Fabrication
09/24/2018
Miscellaneous
Selected 10 CFR 72.48 Screenings
11/01/2018 to
08/03/2020
ASME Section IX Welder Performance Qualifications
05/11/2020,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
06/17/2020,
07/10/2020
20 SFDS Campaign Overall Dose Tracking
08/03/2020
2019 ISFSI Pad 40 CFR 90 and 10 CFR 72.104
Compliance
08/20/2020
Certifications for NDE Personnel
04/23/2020
Qualification Records for Dry Cask Personnel
08/03/2020,
08/19/2020
Fuel Bundle Sipping Records for the Perry 2020 Dry Cask
Campaign
07/27/2020
Cask Fuel Reports for MPC-0919-0496, MPC-0920-0497,
MPC-0921-0498, MPC-0922-0499, and MPC-0923-0500
08/03/2020
2018 Annual Environmental and Effluent Release Report
for the Perry Nuclear Power Plant
03/2019
2019 Annual Environmental and Effluent Release Report
for the Perry Nuclear Power Plant
03/2020
13-140
Change Notice 10 CFR 72.212 Report
08/01/2013
DOC-1025-011
Documentation Package for HI-TRAC 125D for First
Energy (Perry)
RAD 16-02392
Regulatory Applicability Determination Procedure GMI-
213 Rev. 18
Procedures
MC-GTAW
ASME Section IX Welding Procedure Specification
MN-GTAW
ASME Section IX Welding Procedure Specification
GMI-0210
Multi-Purpose Canister (MPC) Loading
GMI-0212
Spent Fuel Dry Storage Ancillary Equipment Preparation,
Inspection and Mobilization
GMI-0213
Multi-Purpose Canister (MPC) Sealing
18, 23, 24
GMI-0213,
MPC Helium Backfill Calculation, MPC #498
08/17/2020
GMI-0215
Spent Fuel Dry Storage Response to Abnormal Conditions
GMI-0220
Multi-Purpose Canister (MPC) Preparation for Loading
GMI-0221
HI-STORM Movement
GMI-0222
Multi-Purpose Canister (MPC) Transfer
HPI-D0005
RP Monitoring Requirements for Dry Fuel Storage Loading
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operations
IOI-19
Spent Fuel Dry Cask Storage
NOP-LP-2601
Procedure/Work Instruction Use and Adherence
NOP-NF-3002,
Verification SNM Physical Inventory Summary,
MPC-0498-0921
08/15/2020
Radiation
Surveys
PY-M-20200808-
Can #22 / 8.177 kW MPC/HI-TRAC Contamination Survey
Hold Point 5.1.1
08/08/2020
PY-M-20200811-
Can #22 / 8.177 kW-MPC/HI-TRAC on Decon Pad Hold
Point 5.5.2
08/10/2020
PY-M-20200813-
Can #22 / 8.177 kW-Post Annulus Drain/Pre-Stack Up
Survey Hold Point 5.7.2
08/13/2020
PY-M-20200813-
Can #23 / 7.408 kW MPC/HI-TRAC Contamination Survey
Hold Point 5.1.1
08/13/2020
PY-M-20200813-
Can #22 / 8.177 kW-Top of HI-STORM/Contamination
Hold Point 5.7.11
08/13/2020
PY-M-20200813-
Can #22 / 8.177 kW-HI-STORM Survey Hold Point 5.7.13 /
ISFSI Survey Step 4.4.1
08/13/2020
Radiation Work
Permits (RWPs)
200315 through
200321
Dry Cask Storage Project
Self-
Assessments
ATL-2018-1297-
ATA-18
20 Perry Dry Cask Loading Campaign Readiness
Review
07/27/2020
MS-C-19-03-30
Fleet Oversight Audit Report: Independent Spent Fuel
Storage Installation (ISFSI)
03/28/2019
SA-BN-2020-
1861
20 Dry Cask Storage Pre-Campaign 4 Self-Assessment
05/29/2020
Work Orders
200692837
Prefab Hi-STORMs/4th Campaign
11/01/2019
200711367
Periodic Crane Maintenance on FHB Crane
05/21/2020
200752617
Special Lifting Device Testing PMI-0120
05/18/2020
200752622
Inspect Dry Cask Storage Concrete Areas
06/20/2019
200752623
Inspect Dry Cask Storage Concrete Areas
07/15/2020
200752641
PMI-0121 Int/Ext Visual Inspection
07/23/2020
200827374
Perform Inspection SFDS ANSI 14.6 Lift Devices
07/22/2020
Drawings
2-0352-00000
Standby Diesel Generator Fuel Oil System
2-0353-00000
Standby Diesel Generator Lube Oil
T
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-0354-00000
Standby Diesel Generator Jacket Water
V
Procedures
SOI-E12
Residual Heat Removal Systems (E12) Rev. 27
2/25/2020
SVI-E12-T1182C
RHR C LPCI Valve Lineup Verification and System Venting
Rev. 19
2/25/2020
VLI-E12
Residual Heat Removal System (E12) Rev. 15
03/26/2019
VLI-R45
Division 1 and 2 Diesel Generator Fuel Oil System (Unit 1)
VLI-R46
Division 1 and 2 Diesel Generator Jacket Water Systems
(Unit 1)
VLI-R47
Division 1 and 2 Diesel Generator Lube Oil
Work Orders
200752000
RHR PUMP C
07/30/2020
71111.11Q Miscellaneous
Evolution Specific
Reactivity Plan
Perry Nuclear Power Plant March 2020 Sequence
Exchange
Simulator Guide
OTLC-3058202009_PY-SGC1
Procedures
FTI-B-0002
Special Maneuver Control Rod Movement Sheet
09/03/2020
Corrective Action
Documents
CR 2020-05132
Greater Than 25 Percent Drop in Battery Voltage When
Starting the Diesel Fire Pump
06/17/2020
CR 2020-06129
Low Specific Gravity on the Diesel Fire Pump Battery
PY-0P5455001B Cell Number Two
08/03/2020
CR 2020-06136
Unplanned Fire Impairment - Diesel Fire Pump Battery Out
of Specification
08/03/2020
CR 2020-06939
Motor Fire Pump Excessive Vibrations
09/04/2020
Corrective Action
Documents
CR 2016-06758
HPCS Diesel Overspeed Trip Occurred Slightly Low
05/24/2016
CR 2020-05711
Improper Functioning of TIP Machine
07/15/2020
CR 2020-06113
Div 3 Start Signal Computer Point did not Show Change in
State on TRA Archive Plot
08/02/2020
CR 2020-06561
Standby Liquid Control Hi/Lo Alarm During Standby Liquid
Control Transfer Pump and Valve Test
08/20/2020
CR 2020-07279
F/D A Combined Vent and Slowdown Valve G36F0013a
Failed Reposition During RWCU Precoat
09/18/2020
CR 2020-07319
RWCU F/D A Combined Vent and Blowdown Valve did
not Make Up Open Limit - Stopped Backwash
09/20/2020
CR 2020-07329
RWCU F/D A Combined Vent and Blowdown Valve
Sticking and Loose Components
09/20/2020
Miscellaneous
GEN-MNT-004-
Material Accountability Log
09/19/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
GMI-0021
Fastener Torque Data Sheet
08/10/2020
IP-ENG-001
Form 4
Design Change Package 19-0095-001
2/10/2020
NOBP-SS-1201-
CDA Impact Analysis
06/11/2020
NOP-OP-1001-12 Zero Energy Checklist (FENOC)
09/19/2020
NOP-SS-1001-02
Software Change Description
06/09/2020
NOP-SS-1001-05 Software Test
06/09/2020
NOP-WM-1001-
Work In Progress Log (WO200825503)
06/26/2020
NOP-WM-1001-
Work In Progress Log
06/01/2020
NOP-WM-1001-
Work In Progress Log
08/08/2020
NOP-WM-1001-
Work In progress Log
09/18/2020
NOP-WM-4300-
Configuration Control Log
08/08/2020
NOP-WM-9001-
FENOC Maintenance Closure Sheet
09/20/2020
Procedures
GEI-0007-A
Instructions for Cable and Wire Terminations
06/19/2020
NOBP-SS-1201-
CDA Impact Analysis
06/08/2020
NOP-OP-1007
Risk Management
NOP-WM-WM-
4300-05
Post Maintenance Checklist
07/21/2020
SOI-E22-B
Division 3 Diesel Generator
Work Orders
200651581
Process Computer
06/01/2020
200684962
Adjust Overspeed Trip Setpoint
08/08/2020
200825503
Firewall
06/25/2020
200832116
Determine Cause of Valve Indication for 1G36F0013A
Being Lost
09/18/2020
200832140
Work Associated with 1G36F0013A
09/20/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 2020-05484
ESW C Discharge Check Valve Did Not Pass Exercise
Open Flow Required by SVI-P45-T2003
07/06/2020
CR 2020-05844
Plant Computer Data Acquisition System Upgrade
Disables TRA Function
07/21/2020
CR 2020-05852
SVI-C51-T5351 LPRM Calibrations Unable to be
Completed Due to No Communication Between Traversing
In-core Probe Machines and Plant Computer
07/21/2020
CR 2020-06561
Standby Liquid Control Hi/Lo Level Alarm During SLC
Transfer Pump and Valve
08/20/2020
CR 2020-06618
Unexpected Seismic Alarm Received
08/23/2020
Procedures
PYBP-POS-0030
Transient Strategies and Mitigating Actions
SOI-C41
Standby Liquid Control System
2/20/2018
SVI-C41-T2001-B Standby Liquid Control B Pump and Valve Operability Test 06/27/2019
SVI-P45-T2003
HPCS ESW Pump and Valve Operability Test
07/06/2020
SVI-P45-T2003
HPCS ESW Pump and Valve Operability Test
07/02/2019
Work Orders
200738424
SVI-E12-T2003 RHR C Pump and Valve Operability Test
07/29/2020
200750879
SVI-C41-T2001B Standby Liquid Control B Pump and
Valve Operability Test
07/31/2020
Calculations
ATL-2020-0553-
ATA-12
DIV3 ESW Flow Change
07/08/2020
Corrective Action
Documents
CR 2020-06249
Failed PMT for HPCS Diesel Heat Exchanger ESW Relief
08/07/2020
CR 2020-06264
Division 3 DG Ran Unloaded for Greater Than 30 Minutes
08/08/2020
CR 2020-06279
Evaluate the Failure Analysis Report from Target Rock for
the 5 Failed Relief Valves (CR 2020 06279) for Further
Actions (if needed) at Perry to Prevent Additional Failures
09/08/2020
CR 2020-06545
Complete a Past Operability Review as Requested by
SARO and Document or Attach the Results (AFTER)
08/26/2020
CR 2020-07380
APRM A Power Adjustment Potentiometer is Giving
Intermittent Voltage
09/22/2020
Corrective Action
Documents
Resulting from
Inspection
ATL-2020-0553-
ATA-17
Plant Narrative Log Typo
07/20/2020
Miscellaneous
IMI-E3-20
Generic Relay Test Data Sheet
09/05/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Measuring and
Test Equipment
Traveler
Measuring and Test Equipment Traveler
08/08/2020
NOP-WM-1001-
Work In Progress Log
08/08/2020
NOP-WM-4300-
Post Maintenance Checklist
09/22/2020
NOP-WM-4300-
Post Maintenance Checklist
08/04/2020
Operability
Evaluations
ATL-2020-0553-
ATA-13
How Does Check Valve Operability Impact DIV3 ESW
Operability
07/08/2020
Procedures
GEI-0135 Rev. 34 ABB Power Circuit Breakers 5KV Types 5HK250 and
5HK350 Maintenance
07/19/2020
GMI-0008 Rev.
Pressure Relief Device Bench Testing
08/08/2020
NOP-WM-1001-
Work In Progress Log
09/05/2020
NOP-WM-2003-
Test Cover Sheet
08/21/2020
NOP-WM-4300-
Post Maintenance Checklist
07/19/2020
PTI-M43-P0005
Diesel Generator Building Ventilation System Damper
Stroking - Division 1
2/05/2019
SOI-P51/52
Service and Instrumentation Air System - Section 7.1
07/20/2020
SVI-C51-T0027-A APRM A Channel Functional for 1C51-K6005A
05/03/2018
SVI-C51-T0027-E APRM E Channel Functional for 1C51-K6005E
05/03/2018
Work Orders
200559679
Remove/Replace Relief Valve
08/08/2020
2005674309
Service Air Compressor, 2P51-C001 Breaker
Refurbishment
05/04/2020
200738804
APRM D Channel Calibration for 1C51-K605D
06/11/2020
200759507
Div1 DG RM Supp Fan 1A Recirc Air Damper
08/18/2020
200773708
DG3 Replace Potentiometer R3 - VOLT Reg. Range
08/08/2020
200821012
Replace Potter & Brumfield MDR Relay 1C71A-KO12A
and 1C7 1A-KO12E
09/22/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 2006-00254
CR for Trending: RTV or Other Sealant is Not Acceptable
for Use in EHC System
01/08/2016
CR 2020-02421
Potential Unacceptable Precondition of SVI-R44-T2001 in
Relation to DIV1 Diesel Generator Run
2/19/2016
CR 2020-07380
APRM A Power Adjustment Potentiometer is Giving
Intermittent Voltage
09/22/2020
Miscellaneous
NOP-OOP-1001-
Zero Energy Checklist (FENOC)
09/22/2020
NOP-WM-1001-
Work In Progress Log
09/16/2020
NOP-WM-4300-
Post Maintenance Checklist
09/24/2020
Procedures
ISI-E22-T1100-2
High Pressure Core Spray (E22) Functional Pressure Test
- Class 2
PMI-0116
Fullers Earth Filter Replacement Instructions
09/22/2020
PTI-GEN-P0012
Total Water Leakage Rate of Primary Coolant from
Systems Outside Containment
10/03/2019
SOI-E12
RHR A Pump and Valve Operability Test
05/25/2020
SOI-E22A
High Pressure Core Spray System
SOI-P42
Emergency Closed Cooling System
SVI-C51-T0027-A APRM A Channel Functional for 1C51-K6005A
SVI-C61-T1200
Remote Shutdown Control Test RCIC and RHR
SVI-E31-T0375
Drywell Floor Drain Sump Flow Monitoring System
Channel Functional for 1E31-K606
TAI-0506
Preparations of Inservice Inspections Instructions
TAI-2000-2
Vibration Monitoring
VLI-R44
Division 1 and 2 Diesel Generator Starting Air System
Work Orders
200738424
SVI-E12-T2003 RHR C Pump & Valve Operability Test
07/30/2020
200738517
SVI-E22-T1200 1 (92D) HPCS Pump Discharge Pressure
- High (Bypass) Channel Functional for 1E22-N651
2/08/2020
20075200
RHR C Pump
07/30/2020
200752935
Replace Fullers Earth Filter/B33 HPU B SL-1
09/24/2020
200754875
Drywell Floor Drain Sump Flow Monitoring System
Channel Functional for 1E31-K606
08/24/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200761516
SVI-C61-T1200 RSD Ctrl Test - RCIC/ RHR
07/21/2020
200761928
ISI-E22-T1100-2 High Pressure Core Spray Pressure Test
- Class 2
2/08/2020
200792554
RHR A Pump and Valve Operability Test
08/18/2020
Miscellaneous
Scenario Guide
Perry Emergency Response Organization Drill Scenario
Guide
Corrective Action
Documents
20-01864
The 20202 Reactor Water to NCC Leakage Methodology
03/06/2020
20-02048
Detectable Tritium Above 2000 pCi/l Detected in Manhole
03/10/2020
20-02224
Tritium Detected in Aux. Boiler Deaerator Drain
03/14/2020
Corrective Action
Documents
Resulting from
Inspection
20-05865
NRC ID: ODCM Procedure Correction
07/21/2020
Miscellaneous
Effluent Monitor Availability Data July 1, 2019 through
June 30, 2020
Various
2018 Annual Environmental and Effluent Release Report
04/29/2019
2019 Annual Environmental and Effluent Release Report
04/17/2020
19-016
Liquid Radwaste Release Permit
03/21/2019
19-092
Liquid Radwaste Release Permit
2/14/2019
19-093
Liquid Radwaste Release Permit
2/15/2019
Procedures
Offsite Dose Calculation Manual
Offsite Dose Calculation Manual
CHI-0005A
Miscellaneous Gaseous Effluent Sampling
CHI-0007
Midas
CHI-0022A
Composites
REC-0104
Chemistry Specifications
Self-
Assessments
SA-BN-2020-
1868
20 Radioactive Gaseous and Liquid Effluents
05/13/2020
71151
Calculations
Radiological Effluent Dose Summary Information July 2019
through June 2020
Various
Miscellaneous
NOBP-LP-4012-
Mitigating Systems Performance Index (MSPI)
Unavailability Index (UAI) and Unreliability Index (URI) for
Emergency Service Water (ESW)
07/01/2019 -
06/30/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PI Summary
Report
Mitigating Systems Performance Indicator Heat Removal
System
07/01/2019 -
06/30/2020
PI Summary
Report
Mitigating Systems Performance Indicator Residual Heat
Removal System
07/01/2019 -
06/30/2020
PI Summary
Report
Mitigating Systems Performance Indicator Cooling Water
Systems
07/01/2019 -
06/30/2020