IR 05000334/2019011
| ML19169A179 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/13/2019 |
| From: | Glenn Dentel NRC Region 1 |
| To: | Bologna R FirstEnergy Nuclear Operating Co |
| References | |
| IR 2019011 | |
| Download: ML19169A179 (8) | |
Text
June 13, 2019
SUBJECT:
BEAVER VALLEY POWER STATION UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000334/2019011 AND 05000412/2019011
Dear Mr. Bologna:
On May 23, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Beaver Valley Units 1, 2 and discussed the results of this inspection with Mr. Rod Penfield, Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Glenn T. Dentel, Chief Engineering Branch 2
Docket Nos.: 05000334 and 05000412 License Nos.: DPR-66 and NPF-73
Enclosure:
Inspection Report 05000334/2019011 and 05000412/2019011
Inspection Report
Docket Numbers:
05000334 and 05000412
License Numbers:
Report Numbers:
05000334/2019011 and 05000412/2019011
Enterprise Identifier: I-2019-011-0016
Licensee:
FirstEnergy Nuclear Operating Co.
Facility:
Beaver Valley, Units 1 and 2
Location:
Shippingport, PA 15077-0004
Inspection Dates:
April 29, 2019 to May 23, 2019
Inspectors:
C. Hobbs, Reactor Inspector
D. Kern, Senior Reactor Inspector
K. Mangan, Senior Reactor Inspector
Approved By:
Glenn T. Dentel, 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 (Programs) inspection at Beaver Valley Units 1 and 2 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations
No findings 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
===71111.21N - Design Bases Assurance Inspection (Programs)
The inspectors evaluated Environmental Qualification program implementation through the sampling of the following components:
Select Sample Components to Review - Primary Containment (Inside Containment)
(IP Section 02.01)===
Unit 2, Power Operated Relief Valve (2RCS-PCV-455C) [solenoid operated pilot valve, position indication switch, wire splice, containment penetration, power cable]
Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside
Containment) (IP Section 02.01) (7 Samples)
- (1) Unit 1, Turbine Driven Auxiliary Feedwater Pump Steam Supply Isolation Trip Valve (TV-1MS-105B) [solenoid valve, cable splice, limit switch]
- (2) Unit 1, Fast Acting Feedwater Isolation Trip Valve (HYV-1FW-100A) [valve actuator, power cable, limit switch]
- (3) Unit 1, Volume Control Tank Outlet to Charging Pumps Suction Valve (MOV-1CH-115E) [motor, valve operator]
- (4) Unit 1, Outside Recirculation Spray Pump (1RS-P-2B) [motor, power cable]
- (5) Unit 1, Containment High Range Area Monitor (RM-1RM-219B) [high range radiation monitor, containment penetration, instrument cable]
- (6) Unit 2, Residual Heat Release Valve (2SVS-HCV104) [valve actuator, solenoid valve, limit switch, power cable]
- (7) Unit 2, Main Steam Flow Transmitter (2MSS-FT485) [transmitter, instrument cable]
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 23, 2019, the inspector presented the Design Basis Assurance Inspection (Programs) Inspection results to Mr. Rod Penfield, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N Calculations
8700-DQC-0024
Namco Limit Switch models EA 180 and EA740 with EC210
or EC290 Receptacle/Connector Qualified Life of 60 Year
License and Post Accident Operability Time for EPU
Revision 7-2
8700-DQC-0225
Siemens-Allis Outside Recirculation Spray Pump Motor
Qualified Life for 60 Year License and Post Accident
Operability Time for EPU
Revision 0
Corrective Action
Documents
CR-2018-07610
CR-2018-08482
CR-2018-08656
CR-2018-08656
CR-2019-00243
Corrective Action
Documents
Resulting from
Inspection
ATA-2019-06673
ATA-2019-06920
CR-2019-04029
CR-2019-04083
CR-2019-04084
CR-2019-04589
CR-2019-04612
EER-601219932,
Continued
Temperature
Monitoring
Engineering
Evaluations
FlowServe/Edward Vogt Valve Co. Valve Actuator Model
Revision 5
ASCO Solenoid Valve
Revision 14
Outside Spray Pump Motors
Revision 5
Radiation Monitors and Cable Connectors
Revision 6
NAMCO EA180 Series Limit Switches with 1/2 EC210
Receptacle Connector/Cable Assembly
Revision 9
Electrical Penetrations
Revision 6
Westinghouse Electro-Hydraulic Actuated Valve
Revision 9
Pressure Transmitters
Revision 8
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NAMCO Limit Switches
Revision 2
Garret / Crosby PORV Solenoid Operated Pilot Valve and
Position Indicating Devices
Revision 8
Duquesne Light company Equipment LIFETIME Monitor
Radiation and Thermal Environment Report for Beaver
Valley Unit 1
Revision 0
FENOC Equipment LIFETIME Monitor Radiation and
Thermal Environment Report for Beaver Valley Units 1 and 2
Revision 1
Miscellaneous
NRC Safety Evalulation Report for Final Resolution of
Environmental Qualification of Electric Equipment Important
to Safety - Beaver Valley Unit 1
03/07/1985
EGS-TR-902200-
Test Report for NAMCO EA-180 and EA-740 Limit Switches
for use in Cooper Nuclear Station,
2/28/1995
Age/Environment Induced Cable Failures
06/16/1986
Safety Evaluation Report Related to the Operation of Beaver
Valley Power Station Unit 2
Supplement
Work Orders
200015627