IR 05000440/2022010
| ML22272A058 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/29/2022 |
| From: | Richard Skokowski NRC/RGN-III/DORS |
| To: | Penfield R Energy Harbor Nuclear Corp |
| References | |
| IR 2022010 | |
| Download: ML22272A058 (10) | |
Text
SUBJECT:
PERRY NUCLEAR POWER PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000440/2022010
Dear Mr. Penfield:
On September 22, 2022, 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, Richard A. Skokowski, Chief Engineering 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-2022-010-0051
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Perry Nuclear Power Plant
Location:
Perry, OH
Inspection Dates:
September 19, 2022 to September 22, 2022
Inspectors:
M. Abuhamdan, Reactor Inspector
J. Bozga, Senior Reactor Inspector
E. Magnuson, Reactor Inspector
Approved By:
Richard A. Skokowski, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline 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.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for Title 10 of the Code of Federal Regulations (10 CFR) 50.59 from June 2019 thru September 2022.
- (1) Evaluation: 21-01636, Off Gas Vault Refrigeration System Abandonment Project
- (2) Evaluation: 19-01265, Manual Lockout Switch for Main Turbine Mechanical and Electrical Trips
- (3) Evaluation: 19-01015, MSIV closure
- (4) Screening: 19-00119, Evaluation of Calculations that Previously Used a Higher than Minimum Specified Design Concrete Compressive Strength
- (5) Screening: 21-01037, SIPE (Structural Integrity Pipe Evaluation) Software, Version 4.01 / RFCA PY20210126
- (6) Screening: 19-01535, Calculation Updates Associated with ECP 18-0087
- (7) Screening: 20-00337, Installation of Hilti Drop-In Anchors
- (8) Screening: 20-00212, Swap Dryer and Separator in Upper Pool
- (9) Screening: 20-00327, Miscellaneous pipe support calculations for replacement of PSA Mechanical Snubbers with Lisega Hydraulic Snubbers
- (10) Screening: 20-00380, Analysis E12G010C Evaluation of Temporary Lead Shielding
- (11) Screening: 19-01544, Interim Flooding Protection for Plant Structures - Ground Level Vulnerabilities
- (12) Screening: 19-01415, Temporary Roof Protection for Flood Mitigation
- (13) Screening: 19-01689, Roof Modifications to Handle PMP, EC 18-0072-001
- (14) Screening: 22-00914, RHR System Heat Exchanger "B" Loop Performance Test Evaluation
- (15) Screening: 19-02205, 1G33F0039 Valve Replacement
- (16) Screening: 22-00595, Evaluation of Required Minimum Thickness of Partition Plate for Division 3 DG Jacket Water Heat Exchanger,1E22B5002
- (17) Screening: 14-04299, Transfer Security Loads to Unit 2 480 Volt Power Supply
- (18) Screening: 13-03461, Installation of isolation valves and appendages on P52 instrument air piping inside drywell to isolate MSIV accumulators - 1 B21A0001A/B/C/D and SRV accumulators - 1 B21A0004R/N/G/K/C/D/H/M/S/J
- (20) Screening: 21-01727, Diesel Generator Fuel Oil Storage Tank Level Instrumentation Upgrade
- (21) Screening: 20-01006, Exclude Vehicle Barrier System's vehicle arrest gates from design control
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On September 22, 2022, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. R. Penfield, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1:14.01.18
Evaluation of Calculations that Previously Used a Higher
than Minimum Specified Design Concrete Compressive
Strength
1C41-A00 1-0004
Structural Qualification 1C41-A001-004
Addendum
Structural Qualification 1C41-A001-001
Addendum
Structural Qualification 1C41-A001-002
Addendum
Structural Qualification 1C41-A001-003
Addendum
Johnson Controls Incorporated Installation/Fabrication
Addendum
Johnson Controls Incorporated Installation/Fabrication
Addendum
1N27G006A A-01
Pipe Stress Analysis of Feedwater System
3.1.2.1
Normal Operation Offgas System Releases
3.2.15.11
MSIV Closure
3.2.15.2.1
Control Rod Drop Accident Radiological Analysis Using
3.2.15.2.1
Control Rod Drop Accident Radiological Analysis Using
3.2.15.2.1 A-03
Control Rod Drop Accident Radiological Analysis Using
50:26.000
EVALUATION OF ROOF DRAIN CAPACITY
50:65.000
Evaluation of Structural Roof Capacity for USAR Described
PMP Event
50:65.000 A-02
Evaluation of Safety Structure Roof Scupper Capacity and
Membrane Capability for USAR Described PMP Event
50:87.000
PNPP Local Intense Precipitation Study Calculation
Calculations
E12-089
Required ESW Flow for the RHR HXs
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
E12-102
RHR System Heat Exchanger "B" Loop Performance Test
Evaluation
E12-102
RHR System Heat Exchanger "B" Loop Performance Test
Evaluation
E22-037
Design Basis Heat Load & Required ESW Flow for the
E22-046
Evaluation of Required Minimum Thickness of Partition Plate
for Division 3 DG Jacket Water Heat Exchanger, 1E22B5002
EA-0084
Analysis E12G010C Evaluation of Temporary Lead Shielding
Addendum
ECA-017
Environmental Conditions Analysis OGB
G33-026 A-07
Proto-Flo Model of RWCU
M52-002
TSC-UPS Battery Room/ Electrical Equipment Area Cooling
and Heating Load Calculations
MOV Report
1G33F0039-007
MOV Report for replacement RWCU Valve 1G33F0039
MOVC-0076
EPRI PPM Thrust Calculation for MOVs 1E51F0063 and
1E51F0064
X0449
Johnson Controls Incorporated Installation/Fabrication
Addendum
X0450
Johnson Controls Incorporated Installation/Fabrication
Addendum
2019-01050
Issues with Motor Received for RWCU Containment Isolation
Gate Valve/Actuator Replacement
2/05/2019
2019-01050
ECP 18-0081 for G33F0039 Requires Revision
2/04/2019
22-03894
Division III Emergency Diesel Generator Jacket Water Heat
Exchanger Partition Plate Thickness Degradation
05/06/2022
Corrective Action
Documents
22-04839
Service Building and TSC UPS Battery Room Fire Barrier
Discrepancies
06/14/2022
Corrective Action
Documents
Resulting from
Inspection
22-07010
22 NRC 50.59 Inspection - Minor Errors in Calculation
3.2.15.11, Rev. 1
09/15/2022
Engineering
2-0214-002
Installation of Isolation Valves and Appendages on P52
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Instrument Air Piping Inside Drywell to Isolate MSIV
Accumulatio-1B21A001A, 1B21A001C and SRV
Accumulators 1B21A004R, 1B21A004N, 1B21A004G,
1B21A004K and 1B21A004C
18-0072-001
Roof Modifications to Handle PMP
19-0155-000
Installation of Flood Barriers at Plant Doors
19-0173-001
Manual Lockout Switch for Main Turbine Mechanical and
Electrical Trips
19-0178-001
Interim Flooding Protection for Plant Structures - Ground
Level Vulnerabilities
19-0178-002
Temporary Protection for Roof Water Levels During Probable
Maximum Precipitation
19-0178-006
Restoration for Protection for Roof Water Levels During
Probable Maximum Precipitation
19-0246-001
1G33F0039 Valve Replacement
21-0154-001
21-0174-001
Off Gas Vault Refrigeration System Abandonment Project
21-0192
Diesel Fuel Oil Storage Tank Level Instrumentation Upgrade
DEER 14-01-01
Transfer Security Loads to Unit 2 480 Volt Power Supply
DEER 20-01-01
Exclude Vehicle Barrier System's Vehicle Arrest Gates From
Design Control
Changes
DSDS-35
RWCU Motor Operated Containment Isolation Gate Valve
Safety Related 6 lnch ASME Class 2
0079-0236-Calc-
2
Installation Verification Calculation for Version 4.0 of the
EPRI PPM Software, Computer Service Tag No. G5J0NV2
ASME 1974 Ed -
Sect III -
Division 1
ASME 1974 Ed - Sect III - Division 1, Rules for Construction
of Nuclear Power Plant Components, Subsection ND class 3
Components
1974 Ed
Commitment
L01916
ESW HEAT EXCHANGER TESTING FREQUENCY
11/11/2014
Miscellaneous
Docket No. 50-
440, PY-
CEI/NRR-1734L,
PY-CEI/NRR-
Perrys correspondence to GL89-13
04/08/1994,
03/01/1991,
01/26/1990
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
28L, and PY-
CEI/NRR-1121
Response to Request for Additional Information Regarding
Request for Deferral of Actions Related to Beyond-Design-
Basis External Events Flooding Actions
03/20/2019
NORM-ER-3420
Nuclear Operating Reference Material, Emergency Diesel
Generator
NORM-ER-3507
Nuclear Operating Reference Material, FENOC Heat
Exchangers
Operability
Evaluations
2015-08036
Prompt Functionality Assessment for Flooding Challenges
NOBP-SS-3140
Nuclear Operating Business Practice, Use of Digital
Signature
NOP-ER-2006
Service Water Reliability Management Program
PTI-E12-P0003
RHR Heat Exchangers B and D Performance Testing
PTI-E22-P0007
HPCS Diesel Generator Jacket Water Heat Exchanger
Performance Testing
Procedures
PTI-N32-P0001
Turbine Overspeed Protection Devices Trip Weekly Test
200415912
(4Y) HPCS Diesel Generator Jacket Water Heat Exchanger
Performance Testing
2/16/2010
200442907
(4Y) HPCS Diesel Generator Jacket Water Heat Exchanger
Performance Testing
05/12/2015
Work Orders
200645158
(4Y) HPCS Diesel Generator Jacket Water Heat Exchanger
Performance Testing
08/27/2019