IR 05000440/2020010
| ML20338A505 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/03/2020 |
| From: | Karla Stoedter NRC/RGN-III/DRS/EB2 |
| To: | Penfield R Energy Harbor Nuclear Corp |
| References | |
| IR 2020010 | |
| Preceding documents: |
|
| Download: ML20338A505 (12) | |
Text
December 3, 2020
SUBJECT:
PERRY NUCLEAR POWER PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000440/2020010
Dear Mr. Penfield:
On November 20, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at 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.
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/
Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety
Docket No. 05000440 License No. NPF-58
Enclosure:
As stated
Inspection Report
Docket Number:
05000440
License Number:
Report Number:
Enterprise Identifier: I-2020-010-0052
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Perry Nuclear Power Plant
Location:
Perry, OH
Inspection Dates:
November 02, 2020 to November 20, 2020
Inspectors:
K. Barclay, Reactor Inspector
A. Dahbur, Senior Reactor Inspector
E. Fernandez, Reactor Inspector
W. Hopf, Electrical Contractor
M. Jones, Reactor Inspector
B. Jose, Senior Reactor Inspector
R. Ng, Project Engineer
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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.
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), regional inspectors were directed to begin telework. Regional based inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. For the inspection documented below portions of the IP were completed remotely and all the objectives and requirements for completion of the IP were met.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)
=
- (1) Emergency Diesel Generator (EDG), Division 2 (1R43S0001B)
- Electrical Steady State and Transient Load Flow, Short Circuit and Voltage Drop Calculations
- Surveillance, Testing and Acceptance Criteria
- Technical Specifications
- Overall System Health
- Fuel Oil Capacity
- Emergency Refueling Capability
- Mission Time of EDGs
- Corrective Actions
- Normal and Emergency Procedures Associated with EDG Operation
- (2) Motor Control Center (MCC) EF1C07 (1R24S0023)
- Electrical Rating and Loading Design
- Voltage Drop for MCC Starters
- Surveillance, Testing and Acceptance Criteria
- Fuse Sizing and Overload Relay Selection
- Maintenance History and Effectiveness
- Corrective Actions
- Cable Protection Calculations (3)125 Vdc Bus ED-1-A (1R42S0024)
- Load Flow, Short Circuit and Voltage Drop Calculations
- Fuse Coordination
- Cable and Bus Ampacity
- Maintenance History and Effectiveness
- Corrective Actions
- Cable Protection Calculations
- Surveillance, Testing and Acceptance Criteria
- Technical Specifications
- (4) Reactor Core Isolation Cooling (RCIC) Pump (1E51C0001)
- Surveillance, Testing and Acceptance Criteria
- Corrective Actions
- Maintenance History and Effectiveness
- Net Positive Suction Head Calculations
- Pump Curve Calculations
- Technical Specifications
- (5) RCIC Discharge Pressure Test Return to Suppression Pool/Condensate Storage Tank Check Valve (1E51F0021)
- Surveillance, Testing and Acceptance Criteria
- Leak Rate
- Corrective Actions
- Maintenance History and Effectiveness
- Design and Installation Requirements
- Technical Specifications
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)
- (1) Residual Heat Removal (RHR) Shutdown Cooling Inboard Suction Isolation Valve (1E12F0009)
- Voltage Drop to the Valve and Minimum Thrust Calculations
- Control Circuit Voltage Analysis
- Thermal Overload Settings
- Power and Control Cable Ratings
- Surveillance, Testing and Acceptance Criteria
- Maintenance History and Effectiveness
- Corrective Actions
Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)
- (1) ECP No. 18-0158-002; Restore the Essential Service Water System Piping Between Valves 1 P45F0550A and 1 P45F0068A with a Reinforcement Pad Installed to the Original Piping Configuration
- (2) ECP No. 16-0039-001; Elimination of the Drain Appendage Attached to 1 B33F0023A in the B33 Reactor Recirculation System
- (3) ECP No. 17-0205-001; Installation of American Society of Mechanical Engineers (ASME) Section Ill Class 2 Thermal Relief Valve PY-1 P11 F0629 on Penetration P111 Piping
- (4) ECP No. 17-0317-001; Revise Overload Relay Heaters and Fuse Size for 1M43C0003B, Diesel Generator Auxiliary Fan B
- (5) ECP No. 19-0091-001; Reclassification of Test, Vent, and Drain Piping from Safety and ASME Class 1,2 or 3 to Non-Safety, Non-Code Class
- (6) ECP No. 19-0178-001; Interim Flooding Protection for Plant Structures - Ground Level Vulnerabilities
Review of Operating Experience Issues (IP Section 02.06) (2 Samples)
- (1) OE-2017-0561-1; IN 17 - 06, Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the Direct Current Distribution System
- (2) OE-2018-0200-1; Multiple Fuse Failures due to Change in Vendor Fuse Characteristic Curve Without a Model Number Change
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 20, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. R. Penfield, Site Vice President, Nuclear and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
Residual Heat Removal (RHR) System Hydraulic Calculation 03/07/2002
2.1.6
Suppression Pool Response - Main Steam Isolation Valve
Closure (MSIVC) and MSIVC with Small Break Accident
(SBA)
2.1.7
Perry Nuclear Power Plant (PNPP) Suppression Pool to
Drywell / Containment Air Mass / Heat Flux - MSIV Closure
DCP 99-5036
R45 System Operating Temperatures
07/15/2002
DRF-699-0001
Containment / Nuclear Safety System Interface Data Book
and Final Safety Analysis Report (FSAR)
03/18/1975
FSPS-0030
Fuse Sizing and Overload Relay Selection for Class 1E 460
Volt Motors
P45-030
Perry Unit 1 P45 System Operating Temperatures
04/15/2020
P45-075
Minimum Branch Flow Rates for P45 Surveillance
Acceptance Criteria
PRDC-0002
Unit 1, Division 1, 2, 3 125 Volt Direct Current (Vdc) System
Coordination
PRDC-0004
Class 1E 125 Vdc Control Circuit Coordination
PRDC-0012
Evaluation of 125 Vdc Loads for a 4 Hours Design Basis
Station Blackout (SBO) and also for a 24 Hours Beyond
Design Basis SBO Events
PRDC-0014
Division 1, 125 Vdc System Load Evaluation, Voltage Drop,
Battery/Battery Charger Sizing Calculation
PSTG-0001
Class 1E Power Distribution System Voltage Study
PSTG-0006
Short Circuit Study
PSTG-0014
Electrical Load Determination of Emergency Diesel
Generators (EDGs) 1, 2 and 3
PSTG-0017
Division 1, 2 and 3 EDG 7-day Average Kilo Watt Loading
for Fuel Oil Consumption
PSTG-0030
Voltage Drop in Control Circuit of Safety Related Motor
Control Center (MCC) Starters
R45-003
Diesel Fuel Oil Pumps
R45-11
EDG Fuel Oil Transfer Pump Performance Requirements
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
R46-0018
Design Basis Heat Load & Required Essential Service Water
(ESW) Flow for the Division 1 and 2 EDG Jacket Water Heat
Exchangers
R46-024
Division 2 EDG Jacket Water Heat Exchanger Performance
Test
2/05/2016
R47-C03
R47 Standby Diesel Generator Lube Oil High Temperature
Trip
Corrective Action
Documents
ATL-2020-0816-
ATA-33
Vendor Required Net Positive Suction Head (NPSH) for the
Reactor Core Isolation Cooling (RCIC) Pump
11/20/2020
CR-2012-11207
Time Critical Operator Action Validation, Suppression Pool
Cooling Actions
07/18/2012
CR-2017-07810
25 Vdc BUS ED-1-A Ground Fault
07/23/2017
CR-2017-08103
Division 2 Auxiliary Exhaust Fan Thermal Overload (T/O)
Tripped
08/11/2017
CR-2017-08216
Potential Trend with Recent Issues Related to Overload
Heater Sizing
08/14/2017
CR-2018-01192
Safety Class of Fuses in MCC Bucket EF1C07-KK
(1R24S0023-0KK)
2/09/2018
CR-2019-02480
Found Cracked Coil in Contactor
03/18/2019
CR-2019-02720
Division 2 EDG Restarted Following Manual Remote
Shutdown
03/23/2019
CR-2020-00738
1E51F004 (RICIC Turbine Condensate to Radio Active
Waste First Shutoff) Failed the Stroke Closed Time
01/30/2020
Corrective Action
Documents
Resulting from
Inspection
CR-2020-08518
20 Design Bases Assurance Inspection (DBAI):
Configuration Control of Calculation PRDC-0002
11/03/2020
CR-2020-08556
20 DBAI Inspection - NRC Question on PYBP-POS-0029
TCOA Requirements for Suppression Pool Cooling
11/04/2020
CR-2020-08806
20 DBAI Inspection: Configuration Control of Calculation
Motor Operated Valve (MOV) 1E12-17
11/13/2020
CR-2020-08974
20 DBAI Inspection: Minor Violation Regarding Perry
Addressing 1E51F0004 Valve Slow to Close
11/20/2020
Drawings
2-0352-00000
Standby Diesel Generator Fuel Oil System
31-0225-00000
Standby Diesel Generator Fuel Oil Storage Tanks
A
Engineering
17-0205-001
Initiation of American Society of Mechanical Engineers
2/19/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
(ASME) Class III Thermal Relief Valve PY-1P11F0629 on
Penetration P111 Piping
18-0305-001
Division 2 Diesel Generator Air Intercooler Tube Plugging
2/15/2018
Engineering
Evaluations
17-03538
CFR 50.59 Screen of Engineering Change Package
(ECP) 17-0205-000
2/11/2018
Miscellaneous
MOV Report 1E12F0009-005
EDG-97-009
Engineering Design Guide - Heat Exchanger Performance
Testing Data Evaluation
ISTP
Perry Operations Manual - Pump and Valve Inservice
Testing Program Plan
Procedures
ARI-H13-P877-
0001
Division 1 Power
ELI-R24
Electrical Lineup Instruction - 480 Volt MCC
ELI-R42
25 Vdc Systems: Batteries Chargers and Switchboards
IOI-0011
Shutdown from Outside Control Room
OAI-1703
2: Time Critical Operator Actions Hardcard
ONI-C61
Evacuation of the Control Room
ONI-R10
Loss of Alternating Current (AC) Power
ONI-R10-1
Loss of Off-Site Power
C
ONI-R10-2
Station Blackout (SBO)
E
ONI-R42-1
Loss of 125 Vdc Bus ED-1-A
ONI-SPI A-5
Division 1 EDG Restoration
ONI-SPI B-4
EH12 System Operation
ONI-SPI B-5
Division 2 EDG Restoration
PY-SVI-
R43T1318
Division 2 EDG Start and Load
01/01/2020
PY-SVI-
R43T1348
Division 2 EDG 24-Hour Run
10/29/2019
PY-SVI-
R43T7000B
Division 2 Emergency Core Cooling System (ECCS)
Integrated Test
03/27/2019
PYBP-POS-0029
Time Critical Operator Action Validation
SOI-R42 (Div. 1)
Division 1 and 2, 125 Vdc Distribution, Buses ED-1-A and
ED-2-A, Batteries, Chargers, and Switchgear
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SOI-R45
Division 1 and 2 Diesel Generator Fuel Oil System
SVI-R43-T7000-A Division 1 ECCS Integrated Test
SVI-R43-T7000-B Division 2 ECCS Integrated Test
SVI-R45-T1321
Standby Diesel Fuel Oil Receipt 31 Day Analysis
Work Orders
045250637
Pipe Break Hazards within the Control Complex
06/19/2018
200262670
(10Y) Simultaneous Start of All Diesel Generators
03/27/2019
200562995
Division 2 Diesel Generator Jacket Water Heat Exchanger
Performance
2/08/2016
200601934
Division 2 Emergency Diesel Generator
05/09/2019
200644387
(2Y) RHR Shutdown Cooling Suction Isolation Valve
Operability Test
03/16/2017
200644902
PY-1E12 Residual Heat Removal
03/17/2017
200701687
PY-1R43 Unit 1 - Division 1 and 2 Standby Diesel
2/10/2018
200706611
Change Set Point Relay NGV18A 27 ED-1-A Bus
09/23/2019
200709775
(2Y) RHR Shutdown Cooling Suction Isolation Valve
Operability Test
03/22/2019
200710535
(24M) Division 2 ECCS Integrated Test
03/27/2019
200713643
PY-1E12 Residual Heat Removal System
03/24/2019
200724450
Division 2 Emergency Diesel Generator
2/15/2018
200728989
SVI-E51T2001 RCIC Pump & Valve (92D) Operability Test
01/20/2020
200728990
SVI-E51T2001 RCIC Pump & Valve Operability Test
04/21/2020
200734150
(24M) Division 2 Standby Diesel Generator 24 Hour Run
10/27/2019
200738368
(92D) ESW System Loop B Flow and Differential Pressure
Test
08/24/2020
200738377
SVI-E51T2001 RCIC Pump and Valve Operability Test
07/21/2020
200738377
RCIC Pump and Operability Test
07/21/2020
200740485
SVI-E51T2001 RCIC Cold Quick Start / PI Verification
01/31/2020
200742993
SVI-R43T1318 Div 2 D/G Start and Load Division 2
2/30/2019
200750868
(92D) ESW System Loop A Flow and Differential Pressure
Test
10/23/2020
200750875
RCIC Pump and Valve Operability Test
10/19/2020
200774443
Division 2 Emergency Diesel Generator
2/18/2018
10